-------
all air is filtered at least once and the air from problem areas is £ . .-
tered two or three times. Ruilding entrances and exits may be provided
with air locks and the building air pressure may be continuously re-
corded to insure that a vacuum is always maintained. Discharge air may
be sampled with high velocity samplers to detect any leakage or by-
passing of the filters.
Water. Process water requirements in a fabrication plant are nominal
so all water is collected, analyzed, and treated if necessary before
release. *
Land. Solid contaminated waste is compacted if necessary and packaged
to minimize leakage and normally sent to a licensed waste disposal site.
Controls would consist of insuring that the container is indeed scaled
and that there is no surface contamination. Burials should not be per-
mitted at fabrication sites where surface water could leach contamina-
tion from a failed container and enter the ground uater. The remaining
control would be test wells to monitor ground water level to permit re-
moval if it should rise to the level of the waste.
Costs. Costs for on-site burial have not been estimated but the cost of
contract burial has been assumed to be $1 per cubic foot exclusive of
packaging and shipping. Packaging costs and shipping costs are assumed
to average $5 and $3 per cubic foot, respectively. Water and air treat-
ment costs were derived from BNW estimates for 1975 and scaled to the
other years based on throughput ratios to 0.6 power. These costs are
presented in Table V-31. The costs for waste control in the HTGR fuel
fabrication plant are not included since the data were not readily
available.
Power Reactor Operation
Technology Summary
A nuclear power plant consists primarily of a nuclear reactor which gen-
erates a hot coolant fluid and a turbine generator plant which converts
the heat energy in the reactor coolant into electricity. At present,
most of the reactors being built are cooled by light water and have
metallic clad fuel rods containing uranium and plutonium oxide fuels.
The high-temperature gas reactor (HTGR) is being developed and initial
operation of large commercial units is expected in 1980. By 1990 about
one-quarter of the power reactor capacity is expected to be HTGR's. The
HTGR uses spherical particles of uranium and thorium oxide coated with
silicon carbide and graphite and placed in a graphite matrix. A third
type of reactor, the liquid metal fast breeder reactor (LMFBR), also is
being developed and is exoected to be introduced commercially in 1986.
Only seven percent of the power reactor capacity is expected to be LMFBR1s
in 1990. The LMFBR is expected to have a liquid sodium coolant and a
stainless steel clad fuel rod containing uranium and plutonium dioxides.
493
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TABLE V-31. ESTIMATED COSTS TO CONTROL RADIOACTIVE RELEASES
FROM FUEL FABRICATION PLANTS
Cost in Thousands of Dollars
Control Component 1975 1980 1985 1990
Air Filtration - UO- Plant
Capital 6,720 8,560 11,550 17,600
Annual Operating 280 357 481 726
Air Filtration - PuO? Plant - ' :
Capital - ' 2,000 7/80 10,600 18,500
Annual Operating 100 370 530 930
Water Treatment - U0? Plant
Capital • 672 857 1,155 1,740
Annual Operating 56 71 96 145
Water Treatment - PuO? Plant
Capital 250 934 1,325 2,320
Annual Operating 50 187 265 464
Solid Waste - U0? Plant
Capital 15 20 26 40
Annual Operating 135 203 333 645
Solid Waste - Pu02 Plant
Capital 3 6 9 15
Annual Operating 7 49 87 224
Operation of pover reactors creates radioisotopes by fissioning uranium
and pluLonium and by absorption of neutron;; in the reactor components.
Most of the fission products remain in the fuel elements and arc shipped
to the fuel reprocessing plants with the spent fuel. A small fraction
escapes from failed fuel or by diffusion through the fuel cladding and
enters the reactor coolant stream.
Reactor components that absorb neutrons to create radioisotopes are (1)
fuel materials, (2) the coolant, (3) boron poison in the coolant, (4)
coolant impurities, and (5) all reactor structural components and fuel
cladding. These radioisotopes remain in the reactor or travel uith the
coolant until they are removed by (1) neutron absorption, (2) gas re-
lease in the off-gas systems, (3) coolant purification, (4) coolant
leakage, or (5) removal of reactor equipment for disposal. The reactor
waste treatment system is designed to collect all gases, liquids, and
solids containing radioactivity and treat them to minimize radiation
releases to the environment. Radioisotopes removed from the liquid and
gas streams are pacl.nged and shipped off-site for burial as solid radio-
494
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active wastes or arc stored in cylinders as compressed gases. Residual
radioisotopes that remain in the effluent liquids from the radwaste
system are diluted to concentrations within the standards when released.
Residual radioisotopcs in the off-gases arc diluted in ventilation air
to concentrations within the standards and released. The radioactive
waste flow diagram for power reactor operation is shown in Figure V-ll.
Forecasting future waste facility capital costs requires considerable
speculation at present. The current designs for waste systems are gen-
erally quite adequate for keeping waste releases far below permissible
limits. However, current reevaluation of radiation limits may result
in reduction of the permissible limits or of actual releases after 1980.
In this study, it is assumed that current waste equipment systems arc
representative of the equipment in operation until 1980 and that- "as low
as practical" systems will be installed on all reactors starting opera-
tion after 1980.
The total quantity of waste releases was determined by analysis of past
solid waste data and by use of the DOSIS computer code.^"'-^ Solid
waste data were collected for operating reactors and analysed to deter-
mine typical waste generation rates.
The DOSIS code computes the quantities of liquid and gaseous wastes gen-
erated and than follows them through the waste treatment facilities to
determine the amount (.hat is released.
The computations in the DOSIS code are based upon Safety Analysis Report
(Westinj'house ref. SAR,(V~W) Verplant SAR,(V-15) and Fort St. Vrain
SA1<(V-16)) (jata that represent equilibrium conditions. A follow-on
study should undertake a comprehensive evaluation of the generation of
radioactive isotopes in the coolant.
The capital and operating costs estimates for the waste treatment systems
in existing reactor plants were based on the data ir ORNL-4070.(v~ ^)
The capital costs for reactors started up after 1970 were obtained from
the CONCEPT^'"18) computer code of Oak Ridge National Laboratory of OKNL.
Emissions
There are three general types of radioactive wastes generated at power
reactors—gaseous, liquid, and solid. A treatment system is provided
for each type. Other significant environmental impacts result from heat
releases and use of land.
In order to permit completion of this study as scheduled, several simpli-
fying and general assumptions for description of the reactors and their
effects on the environment were necessary. These were:
o Defective fuel includes faulty welds which leak only gaseous fission
products and cracks which release the full spectrum of fission products.
495
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Fresh
Fuel Elements
Power Reactor
Internal Disposal
Irradiated
Fuel Ele-cnts
Gross Residual
(Radioisotopcs)
1
Treatment
(Storage, Filtration,
Doiom'zation,
Distillation)
Treated Residual
Transfer
(Solid Wastes)
External
Contract
Disposal
Air and Water
Receptors
(Radioisotopes)
FIGURE V-L1. POWER REACTOR OPERATION
-------
e Decommissioning will not be considered.
o Liquid wastes from HTGR's and LMFBR's are decontamination wastes,
laboratory wastes, and laundry wastes after treatment.
e HTGR waste treatment is based on the Fort St. Vrain FSAR, plus
bottling of rare gases for shipment to a permanent disposal site.
o LMFBR waste treatment is based on studies by Uestinghouse Hanford
Company.
Air. Radioactive gaseous wastes result primarily from release of fission
product gases from failed fuel elements and absorption of neutrons by the
reactor coolant and impurities in the coolant. These gases then are e-
volvcd from the coolant, particularly following pressure reductions during
reactor outages and coolant purification operations, or from condenser
vents.
The radioactivity of t.he gases is reduced primarily by decay, filtration,
condensation, or absorption on activated charcoal. Decay occurs during
storage in tanks or on charcoal beds for as long as several years. The
gases are then filtered and released through the air ventilation exhaust
system'or sent to permanent disposal in suitable containers.
The radioactive gases released to the ventilation systems travel with the
ventilation air mid are released to Lhc environment when the vcntilaLi.on
air leaves the ventilation stack. The gaser. continue to follow that air
as it mixes with the atmosphere and arc gradually diluted and dispersed
in accordance with the turbulence of the. atmosphere. Simultaneously, the
quantity of radioactivity gradually decreases as the radioisotopes decay.
Radioactive participates released to the atmosphere will gradually settle
out or be washed out in accordance with the size of the particulates and
the type weather. Noble gases generally will remain mixed in the atmos-
phere.
The radiation dose received by humans as a result of releases are depen-
dent on many variables such as quantities of radionuclides released,
locations of the people, and atmosphere conditions. The dose resulting
from operation of a reactor can be predicted reasonably accurately only
by a detailed study considering all variables for that reactor.
Water. Liquid wastes result from reactor coolant system leakage, reactor
coolant purification, and numerous miscellaneous sources, such as laundry
drains, equipment decontamination, pump seals, etc. The liquid wastes
are collected in holding tanks, analyzed for radioactivity, treated (if
necessary) to reduce the radioactivity, and then either re-used or released.
The treatment usually is evaporation or ion exchange. The still bottoms
or spent resins being handled as solid wastes.
497
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The released radioactive liquids generally arc released into the circula-
ting water effluent system which Llicn carries the radioisotopcs into the
receiving body. The release rate is such that the effluent is below the
maximum permissible concentration. As a general rule, the receiving body
is large enough or has a high enough continuous flow so that the radio-
isotopes are diluted to concentrations far below the maximum permissible
under government standards.
The radiation dose received by humans using the water containing the
radioisotopcs depends primarily on the radioisotopes concentrations,
the use of the \«iter, and the contact time for the human. Typical
examples of the human activities that result in dose are: .
o Drinking
o Swimming
o Consuming aquatic life
9 Boating
e Consuming foodc irrigated with the contaminated viator,
The. dose received by humans as a result of releases to water is dependent
on many variables. Again, the dose resulting from operation of a reactor
can be predicted reasonably accurately only by a detailed study considering
all variables for that reactor.
The quantity of cooling water required for removing the waste heat depends
on the reactor thermal efficiency. An LVJR re-quires about 1500 cfs of flow.
The HTGR and LMFBR probably will nctd only about 1100 cfs. Part of this
cooling water is evaporated during transfer of the heat to the atmosplicre.
Tho amount of evaporation is essentially zero for cooling wi th cold ocean
water. On the other hand, a mechanical draft cooling tower may evaporate
as much as 50 cfs.
Almost all plants built prior to 1970 used once through cooling. Host of
these plants will probably continue to utilize this cooling method. A
1969 study by Uice and Colc(v~^) estimates that the heat sink capacity
of major streams in this country would soon be used up. They broke the
country down into 9 regions as shown in Figure V-12 and accumulated stream
flow and temperature data for all rivers in the United States with minimum
monthly average flows greater than 1000 cfs. In estimating the energy
which could be added to each stream, they used the average flow in the
month witli the lowest total run off in the 1956-1966 time period. Table
V-32 compares the anticipated projected increase in heat load from electri-
cal plants built between 1965 and 1980 with the heat dissipation ability of
the streams. It can be seen that in almost every area of the country, there
is insufficient heat dissipation capability in the major streams.
498
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O
O
FIGISE V-12. REGIONAL DIVISIONS
-------
TABLE V-32. COMPARISON OF PROJECTED HEAT RELEASED FROM
THERMAL POWER PLANTS BUILT BETWEEN 1965-
1980 WITH THE HEAT SINK CAPABILITY OF THE
STREAMS
Region of
Country
1
2
3
4
5
6
7
8
9
Total or Average
Projected
Additional Power
Generation 1965-1980
39
69
26
74
48
110
85
74
33
558
Heat
Sink Capability
of Streams
in Region
27.64
5.80
10.96
24.36
4.56
8.60
7.68
6.36
60.48
156.44
Percent
of
Capacity
140
1190
240
300
1050
1280
1110
1160
55
(avg.)356
The growth in regions 3, 5, 6, and 9 accounts for about 40 percent of the
total increase in electrical demand. Except for region 9 cooling Lowers
or ponds vill have to be installed for almost every new plant in that
area. The remaining 60 percent of the expected growth in capacity proba-
bly will be met by a combination of plants with ocean and tower coding.
If it is assumed that one-half of these plants have ocean cooling, one
obtains a 70 percent/30 percent split between once through and close
cycle cooling for all plants aftc-r 1980. Prior to 1980, there will be a
build-up toward the 70/30 split since all plants built prior to 1970 will
probably continue to une once through cooling. In 1975, based on present
trends, about 20 pcrcp.nt of all nuclear reactors will be utilising once
through ocean cooling, 30 percent will be using cooling towers, and 50
percent will still be using once through fresh water cooling. By 1980,
the percentages using once through cooling and closed cycle cooling will
probably reverse. Based on these trends, Table V-33 was constructed to
quantify the probable quantities of waste heat sent to the various re-
ceptors during the 1975-1990 time period.
Land. Each nuclear reactor is built in an exclusion area in which un-
restricted public occupancy is not permitted. This exclusion area is
designed according to the siting requirements of 10C1TR100 which concern
safety aspects of the facility. The size of the exclusion area is de-
pendent on the reactor size, the design of plant safety systems, and the
local meteorology. For a reactor which incorporates "as low as practicable"
technology to control routine radioactivity discharges, the continuous
radiation dose received by a person residing permanently at the edge of
500
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this exclusion area will satisfy the limits specified iA proposed Appendix
I to 10CFR50. Actual power plant sites usually are larger than the
exclusion area and range up to several thousand acres.
TABLE V-33. RECEPTOR LOADINGS FOR HEAT DISSIPATED
FROM NUCLEAR POWER REACTORS
Gigauatts/Yoar
Receptor IS 75 1980 1985 1990
Streams and Rivers
Atmosphere
Ocean
53
32
21
72
100
60
72
253
126
72 -
504
233
The land actually occupied by the power plant is relatively small--on
the order of twenty acres. The land required by the transmission system
can be quite large, depending on the length of new line that must be
built. As an example, a 300-foot wide right-of-way will occupy about 36
acres of land for each mile of length. In many cases, though, that land
can still be used for agriculture.
Solid wastes consist of gas bottles, still bottoms, spent resins, obsolete
or failed equipment, and miscellaneous wastes, such as'paper, rags, used
clothing, etc. Most solid wastes are packaged in 55-gal.lon drums, with
or without concrete for shielding or solidification. Larger items require
other appropriate containers designed priiMari1y to prevent release of
radioactive materials during handling. All solid wastes are shipped off-
site for burial at licensed waste disposal sites.
Because radioactive solid wastes are not released to the land, there should
be no radiation dose to humans as a result of direct contact with the
radiolfsotopcs. There is a small dose, though, that results from trans-
portation of the wastes to the burial ground. As a general riilo, the
wastes are transported several hundred miJcs from the reactov plant to
one of the few licensed commercial burial grounds. The drums of waste
travel on trucks without external shielding. Persons in cars on the
highways and in adjacent land area will receive radiation as the trucks
pass by. Preliminary calculations indicate that this total dose for a
1000 MWe reactor is small (<0.1 man-rom/yr).
The quantity of solid radioactive wastes shipped to licensed burial grounds
is dependent on the design of the radwastc systems. For "as low as
practicable" systems the quantity is estimated to be from 1000 to 1700
drums per year per reactor.
Summary of Emi ssion. Assuming that the HTGR's and LMFBR's have about the
same environmental impacts as do LWR's, the potential, environmental im-
pacts can be expressed in terms of the impact per 1000 Mtf plant as shewn
501
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in Table V-34. The total quantity of radioisotopes released in each of
the four years considered in this study is presented in Table V-35.
TABLE V-34. POTENTIAL ENVIRONMENTAL IMPACT OF
POWER OPERATION
Parameter
Typical Values per 1000 MWe Reactor
Heat releases
Radioisotope releases(
To air
To liquids
To burial
Land occupancy
Transmission lines
Exclusion area
Plant occupancy
Water evaporation
Cooling water flow
1500 to 2000 MW
curies/yr
curies/yr
curies/yr
1000 to 1700 drums/yr
36 acres/mile
100 to 500 acres
^20 acres
Up to 50 cfs
1100 to 1500 cfs
TABLE V-35. POWER REACTOR OFERATION-RADIONUCLIDE
RELEASES TO THE ENVIRONMENT
Curies
Water
Year
1975
1980
1985
1990
Air
9.4xl06
2. 0x10 7
2.6xl07
3.9xl07
Lithium
2.7xl05
S.OxlO5
1.8xl06
3.9xl06
Others
339
1,013
3,430
8,500
Control Mechanisms and Costs
The location and amount of heat released to the environment is controlled
by the design of the cooling system. The choices range from the simplcr
once-through cooling systems on water bodies, which discharge all heat
into the water body, to costly dry cooling towers, which discharge all
heat to the air. The design selection is based on the environmental con-
ditions around the individual reactor plants. The total installation cost
ranges from about $8,000,000 for the simple once-through system to as much
502
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as $80,000,000 for dry towers. The annual operating costs range from a-
bout $500,000/ycar to as much as $8,000,000/year, exclusive of capacity
penalties.
Some power plants have supplemental cooling towers that are operated only
during critical periods of the year--such as the summer period when high
river temperatures exist. Such systems generally are operated whenever
undesirable water body conditions exist or during all weather conditions
that do not result in undesirable water body conditions fogging or icing.
Release of radionuclides generally is controlled by (1) the design of the
radwaste systems, and (2) the mode of operation of the radwaste systems.
The initial control decision is the design decision since this- generally
determines the maximum treatment possible for the raduastes. The actual
design can vary from essentially 2ero treatment of the wastes before
release to the environment to intensive treatment resulting in "as low as
practicable" or essentially aero release. The corresponding capital costs
vary from about. $3,000,000 to about $15,000,000 per reactcr, and the
annual operating costs from about $40,000/year to about $500,000/year per
reactor.
The method of operating the raduaste system will determine the amounts of
releases, particularly to water bodies. The. most convenient method is to
operate the. system such that the releases result in radioisotopc concen-
trations or doses well below permissible limits. It is possible, though,
in some cacus to operate thfc systems more intensively in combination with
maximum recycle of treated water such that there is a much smaller re-
lease rate. Such operation ir.ay not be justified economically by the
resultant minor reduction in the amount of radioisotopes released or in
the reduction of population radiation dose, but may be justified from a
political standpoint. The increase in total radiation dose received by
plant employees may be more significant than the usually trivial re-
duction in dose to the general population.
Release of chemicals to water bodies generally are controlled by releasing
the chemicals at a low enough rate thct tha dilution by the flow in the
receiving body reduces the concentrations below applicable government
standards. The operating costs for accomplishing such dilution generally
are trivial. Generally, the extra construction cost for assuring proper
dilution is trivial, but occasionally costs up to $1,000,000 may be
necessary if special diffusers or long pipelines must be used. Similarly
costs up to $1,000,000 mr.y be necessary if a satisfactory water body is
not available so that seepage or evaporation ponds must be used.
Releases of sanitary wastes generally are controlled by construction of
sanitary treatment systems designed to meet government standards. Control
then consists only of periodic inspection and maintenance, as appropriate.
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Fuel Reprocessing
rTechno1or.y Summary
Fuel assemblies which reach their goal exposure are discharged from the
reactor, cooled (aged) and transported to the reprocessing plant. In the
reprocessing plant the uranium, thorium and plutonium are separated from
the wastes.
In the 1975-to 1990 time period, 95 percent of the reprocessed fuel will
be irradiated in a LWR. The reprocessing technologies for HTGR, LWR, and
LMFBR fuel are quite distinct at Lhe head-end of the process. However,
for the v:aste handling step the differences are very small," In addition,
no commercial'LMFBR or HTGR reprocessing plants have been built. When all
these facts are combined the resulting conclusion is that the environmen-
tal impacts of the reprocessing industry can be most accurately assessed
by using LWR reprocessing technology for tach reactor concept.
The spent fuel from the reactor is transported from the reactor to the
reprocessing plant in heavy shielded casks. The cask is unloaded and the
fuel stored in a large water-filled pool. The fuel elements to be re-
processed are transferred to the head-end of the plant where the assem-
blies are sheared into 2-inch lengths to expose the fuel. The fuel is then
dissolved with nitric acid in batch dissolving tanks. The leached hulls
constitute a solid waste that is ultimately disposed of by land burial.
During dissolution, volatile gases are released from the fuel and are
collected in a gaseous waste processing system. The nitric acid solution
of the fuel, containing uranium, plutonium, and nearly all the fission
products is the feed solution to the solvent extraction process.
Nearly all major reprocessing facilities employ some form of Purex
process(V-20) which makes use of the organic complexing compound tributyl
phosphate (TBP), in an inert hydrocarbon diluent. Countercurrent extrac-
tion with the aqueous phase extracts the uranium and plutonium into the
organic phrse and leaves the fission products in the waste phase.
The containment of the volatile fission products, especially l!31 is one
of the most difficult problems in reprocessing. The gaseous wastes from
the reprocessing steps are treated Chemically as well as by filtration,
sorption and scrubbing in order to reduce their radioactive content to
levels that can be discharged to the atmosphere.
The LWR fuel being reprocessed has normally been cooled at least 150
days. At this time tritium, Kr85 and iodine are the important gaseous
wastes. Inorganic iodine is removed by reaction with AgN03 impregnated
on ceramic packing and by scrubbing with Hg(N03)2-HN03 or caustic
solutions.(V-*l) Organic iodine, particularly methyl iodide, can be re-
moved most efficiently by catalytic decomposition and sorption on silver,
copper or iodine-impregnated charcoal. The efficiency of the iodine units
is dependent on the concentration of iodine. A 99.6 percent efficiency
is a commonly quoted design efficiency in cases where organic iodides are
504
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not removed.' ' With organic iodine treatment, efficiencies of 99.99
have been quoted, (v"23)
At the present time most reprocessing plants treat the off-gas streams
only for iodine and participates. Particulars arc removed by sand
filters, ™~2 i) deep bed fiberglas filters or a bank of high efficiency
participate air filters. Noble gas collection using cryogenic distilla-
tion^"^) or absorption in f. luorocarbons(v~26) are possible. There is
no currently available tritium removal system.
It can be anticipated that all radioactive liquid wastes from fuel re-
processing will be evaporated and blend c-d to yield only two streams: a
high-level waste consisting of a highly concentrated solution of fission
products and actinides and a low-level aqueous waste that has been
sufficiently decontaminated of. radioisotopes to permit it to be either
discharged to the environment or recycled to the process.
Past practice has been to store the high level liquid wastes in large
underground tanks. This process will probably be curtailed because of
the difficulty in providing cafe containment of the wastes from highly
exposed power reactor fuels. Adequate liquid storage systems may simply
be too large and costly as compared to the cost of early solidification.
Solidified wastes would then be stored on site for several years prior to
shipment to an off-site government repository.
In addition to the high-level aqueous treatment system, large volumes of
process water containing lev/- level wastes are also present. Two to 500
gallons of contaminated water are produced for each metric ton of fuel
processed. These streams, which contain about .1 percent of all the
fission products, can be decontaminated by a factor of 10^ for nil iso-
topes except tritium. At the present time tritium must cither be dis-
charged into the area streams or sent into the atmosphere as water vapor.
The following paragraphs taken from an Oak Ridge summary report:' '
puts the tritium discharge levels in perspective.
Tritium is produced in the fission of U and PU» vich yields of
about 0.01 percent and 0.02 percent, respectively. '' It merits
special consideration from the standpoint of its management in fuel re-
processing because it is unresponsive to separation and concentration by
conventional procedures for treating waste. (V-28,V-29) jn fuci repro-
cessing, less than 1 percent can he expected to volatilize during the
dissolution of oxide fuels. (V-30) There is experimental evidence that
tritium tends to escape from oxide fuels during reactor operation; (
however, the tritium remaining with the fuel can be expected to appear
as tritiated water in the reprocessing plant evaporator condcnsates.
If this tritium could be uniformly dispersed throughout the environment,
the resulting increase in background would be of little significance.^ '
In the actual case, however, a fuel-processing plant will have only its
immediate environs available for dispersion, and the capacity of these
environs to accept tritium will depend on the rate that the latter is
505
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If the.
released, as well as on the many environmental factors that pertain to the
particular site.
Two immediately available possibilities for the release of tritium-bear-
ing wastes under existing regulations are: (1) dilution and release
directly to surface waters, and (2) distillation into the plant off-gas
system and subsequent release up the stack.
The quantity of tritium that can be released to surface waters can be
computed within the limitations that the concentration shall ngt exceed
the permissible concentration in water under 10CFR20, or 3x10 u-c/cc at
the boundary of the controlled zone, and that the concentration shall
subsequently not exceed 1x10° jic/cc for the general population. If t
controlled zone borders a stream of any significant size, the first ot
these restrictions is controlling.
A ton of fuel irradiated to a burnup of 33,000 MWd contains about 700
curies of tritium, which would require dilution in water to the extent
of about 63 million gallons before it could be released from the con-
trolled zone at the permissible concentration of 3.10 |j,c/cc. The
total aqueous effluent from a plant operating with a Purcx process flow-
sheet may be as much as 106 gallons per ton of fuel processed, but this
is far short of the requirements for tritium dilution. The most
practical means of achieving the on-site dilution requirements would ba
to have available, for this purpose, a stream flowing through the con-
trolled area. To meet the specification for use by the general popula-
tion, this stream would have to flow into a larger body of water to
achieve additional dilution by a factor of 3 or more.
It is desirable that a plant be situated adjacent to a large, preferably
navigable, river for other (and possibly more important) reasons than
tritium disposal; however, it is much less obvious that acceptable sites
should be limited to those which, in addition, ci.compass a stream of
the size useful for dilution. Therefore, we conclude that, with re-
strictions as presently interpreted, the alternative of release to cur-
face waters is of very limited applicability as a general case.
Distillation into the plant off-gas provides a more effective means of
releasing tritium. Calculations presented in Section 8 of Reference V-21
indicate that plants having spent fuel capacities up to 20 metric tons
per day and site boundaries two to three km distant can release their
tritium in this manner under existing regulations. This is not to imply,
however, that attempts should not be made to develop methods for re-
moving tritium, before it becomes greatly diluted with air or process
streams, and encapsulating it for a long-terra storage.
Emission
In this section the emissions will be expressed in terms of a 5 ton per
day reprocessing plant operating at 75 percent capacity. In one year
this plant has a throughput of 1370 metric tons of heavy metal. This is
506
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equivalent to the discharge from reactors having a total, installed capaci-
ty of 50 GW. Table V-36 shows the projected de.mand for 'fuel reprocessing.
Current plans project a 1986 startup date for Lhc HTGR plant. Thus, no
fuel reprocessing demand is shown in Table V-36 until 1990 for the IITGR.
The environmental impacts of plant operation on the air, water, and land
will be discussed sequentially. A waste flow diagram for reprocessing is
shown in Figure V-13.
TABLE V-36. REPROCESSING PLANT THROUGHPUTS
Me trig .Ton /Yoa r
LWR
HTGR
LMFBR
1975
1300
0
0
1980
3400
0
3
1985
5500
C
7
1990
10,100
820
540
Air. The emissions from the reprocessing plant operations to air are
"summarized in Table V-37. The reprocessing plant has two major impacts.
One is the release of radioactive gares and pari.iculates. The second is
the decay heat from the radioactive materials in the reprocessing plan!.
Tn addition sonic iodine and sor.ie volatile rare earth chemical compounds
are released. The technology exists to routinely collect these gases.
It is assumed tlinu all new reprocessing plants coming on line after 1975
will be able to remove 99.99 percent of all the radioactive gases.
The table on participate and gas releases was left blank since their
major effect was included under the radiological release heading.
In calculating the heat load, the energy released through radioactive
decay was assumed to be released directly to the air. Another source of
heat is the evaporators and concentrators in the reprocessing plant. It
was estimated that this load was about equal to the heat generated by
radioactive decay and this heat was taken up by Lhc process cooling water
stream.
Water. The major environmental impact of a reprocessing plant on water
results from the requirement for large volumes of process water. It is
estimated that a 5 MT/day reprocessing plant needs about 2,600 gpm of
process and cooling water.^ Older plants discharged some waste
streams from the plant. However, newer plants continually clean up and
reuse all their process water and a cooling water system would be uncon-
taminatccl. The releases to water are summarized in Table V-38. There are
no radiological releases to the water from any plants other than these
already licensed. As was mentioned in the section on air releases, half
507
-------
Irradiated
Fuel
in
O
Go
Nuclear Fuels
Repracesslng
U03, or l'F6;
Pu(NO,), Solution
6> ?jQ
Internal Disposal
RadlorvjcUde
Wastes
MARKET
EXTERNALITIES
Treat
cent
5 Year
0
Htgh Leve
! *
Mr, Lend, Water
Receptors
Solldifl
of
Liqui
Storage
f
1 Wastes
i
cation
ds
External
Contract
Disposal
FIGURE V-13. NUCLEAR FUELS REPROCESSIKG
-------
the thermal load on the reprocessing plant was assumed to be discharged
in the cooling water stream. The bottom part of Table V-38 summarizes the
projected heat loads on the water for all the reprocessing plants in the
time period of interest.
Land. The reprocessing plant, produces both high and low level radioactive
wastes. Both will be solidified to minimize their mobility and then
shipped off site for disposal. Table V-39 gives the curies and volumes of
high level waste shipped off site. It is assumed that they have been
stored for five years on site prior to shipment for perpetual storage at
a government repository. It is estimated that 200 ft^ of low level waste
are generated for each ton of fuel reprocessed.(V~21) The major source of
radiation from the low-level wastes is the cladding hulls. The curies and
volumes of these wastes packaged and tent 'co a licensed contractor are
shown in Table V"AOU It is assumed that these waster, are transported soon
after the fuel h£4s been reprocessed.
Control Mechanisms and Costs
The LMFBR, 1ITGR, and the LWl reprocessing plant waste treatment systems
can be considered to be similar even though the processes are quite
distinct.
The primary sources of waste are: the fission productions separated from
the thorium, uranium, and plutonium recycle streams; the trans-plutoniuip
isotopes; small percentages of the uranium, thorium, and plutonium; and
activated or contaminated processing material.
TABLE V-37. ENVIRONMENTAL EFFECTS OF FUEL REPROCESSING ON ATR
3-975 1980 _19B5 1990
Radiological Curios/Year
LWR • 1.0x10? ].7xlO? 1.9x107 2.1x.l07
HTGR 9.5xlO^>
LMFBR small small 4.7x105
Total 1.0x107 1.7x10? 1.9x10? 2.2x107
Participate and Gas Tons/Year
. LV.'R
HTGR
LMFBR
Total nil nil nil nil
Thermal
MW
LWR 24 62 100 180
HTGR 0 0 0 30
LMFBR 0 <1
-------
TABLE V-38. ENVIRONMENTAL EFFECTS OF FUEL REPROCESSING
ON WATER
1975 1980 1985 1990
Radiological Curies/Year
LWR 2xlOA 2x10* 2xl04 2x10*
HTGR 0000
LMFBR 0 00 0
Total 2x10* 2x10* 2x10* 2xl04
Water Usage - Gpm
LWR 3,000 7,000 11,000 20,000
HTGR 0 0 0 1,600
LMFBR 0 nil nil 2,200
Total 3,000 7,000 11,000 24,000
Thermal GWt
LWK
HTGR
LMFBR
Ttoal
2 4
0
0
24
62
0
<1
62
100
0
<1
100
180
30
20
220
The reprocessing plant waste treatment systems can be subdivided into
gas, liquid, and solid treatment systems. Ultimately the solid and
liquid streams arc combined so only two systems arc needed. The gas
treatment systems are estimated to comprise about 10 percent of the total
reprocessing plant cost.(V-33) Thus, based on 1970 costs, the gas
treatment facilities for a 5-ton per day plant valued at 66 million would
cost 7 million dollars. The annual operating cost of these facilities is
about 1 million dollars. In the near future additional off-gas treat-
ment facilities to collect, noble gases will probably be required. It is
estimated that the additional treatment would add another 10 percent to
the total plant cost.(v~2i) -phus, in the near future many plants may be
required to add additional off-gas treatment equipment which will cost
about 7 million dollars to procure and install. The annual operating cost
of the plant will probably increase by about 1 million dollars a year as
a result of this additional equipment.
The costs incurred from the solid waste treatment facility are not very
sensitive to the process used. For this analysis it will be assumed that
the wastes are immediately solidified and then stored for five years prior
to sending them to the government waste repository. For a 5 ton/day re-
processing plant, the waste treatment facility total installed cost is
estimated to be about 18 million dollars. Annual operating costs are
estimated to be $1.9 million/year.(V-21.V-34)
510
-------
TABLE V-39.
CURIES AND VOLUMES OF HIGH-LEVEL WASTE SENT TO
A GOVERNMENT REPOSITORY FOR PERPETUAL STORAGE
LWR
HTGR
LKFBR
Total
1975
curies/yr
0
0
0
0
0
ffVyr
0
0
0
0
1980
curies/yr
1.3x10
0
0
1.3x10
9
9
•3
ft°/yr
1300
0
0
1.3xl03
1985
curies/yr
3.4x"109
0
4x1 06
3.4xl09
•3
ftVyr
3400
0
3
3.4xl03
1990
curies/yr
5.5x1
0
8x1 06
6.5x1
O9
O9
ft
5.
7
5.
O
Vyr
5xl03
0
5x1 03
TABLE V-40. CURIES AND VOLUMES OF LOW LEVEL WASTE PACKAGED AND SENT TO
A LICENSED REPOSITORY FROM THE REPROCESSING PLANTS
LWR
HTGR
LMFBR
1975
curies/yr ft°/yr
2.9xl05 2.6xl05
0 0
0 0
1980
curics/yr ft /yr
7.5xl05 6.3xl05
0 0
7.4xl05 6.8xl05
1985
curics/yr ft /yr
1.2xl06 l.lxlO6
0 0
1.7xl06 1.4xl03
1990
3
curies/yr ft /yr
2.2xl06 2.0xl06
<105 l.lxlO5
1.3xl08 1.6xl05
6
8
Total 2.9xlOJ 2.6x10° 1.5x10" S.SxlO"' 2.9x10" 1.1x10" 1.3x10° 2.3x10
-------
Radioactivc Wastc Disposal
Technology Sumniary
The solid radioactive wastes generated by the nuclear power industry are
classified primarily in accordance with the level of radioactivity and
the disposition of the wastes. A flowsheet is given in 1'igure V-14.
The high-level wastes are defined as the wastes containing most of the
radioactive fission products separated from the irradiated fuel elements
at the reprocessing plants. These intensely radioactive materials produce
most of the highly-penetrating radiation in the nuclear power industry
outside of the reactor primary loops and also contain significant quanti-
ties of plutonium. They currently are scheduled for storage in special
repositories with an extremely low probability of release to the environ-
ment.
The low-level wastes arc defined as all other radioactive wastes and
generally have relatively low radiation levels even without shielding.
Because of these lower radiation levels, it is considered satisfactory
to package and store them in locations where they can be collected for
eventual burial at licensed waste disposal sites.
Currently low-level radioactive materials generated in the nuclear power
industry are packaged in leak-proof containers for transit (usually 55-
gallon drums) and shipped off site to commercial burial sites. These
materials consist of a multitide of items such as floor sweepings, spont
resins, vaste still bottoms, failed or obsolete equipment, etc. Most of
it contains relatively small amounts of radioactivity; but some, such as
burned-out power reactor control rods, contain thousands of curies of
radioactivity.
When the materials are received at the disposal site, they are simply
dumped into a burial trench and covered with a layer of dirt. The trenches
are built in locations where the expected eventual failure of the Wcisce
containers is not expected to result in travel of the radioactive materi-
als away from the burial site. This is achieved by choosing locations
where the materials will be stored above the water table and there is
little probability that the wastes would be washed down to the water table.
As a general rule, however, the radioactivity of these wastes is low
enough that the burial sites could be re-entered and wastes repackaged,
if environmental monitoring shows that there could be an uncontrolled
release to the environment.
There is no treatment of surface burial wastes at the burial sites. The
shipping containers are designed to prevent release of radioactive materi-
als during transportation and burial.
High-level radioactive wastes currently are stored as liquid solutions in
tanks. After 1975, all sucli wastes are expected to be solidified and
stored in permanent engineered storage. Economic analysis shows that the
512
-------
Radioactive
. Wastes
Waste Receiving
Operation
Gross Residuals
(Waste Materials)
Internal
Disposal
Untreated
Residual
Land Receptor
(Burin! Site)
FIGURE V-1A.' RADIOACTIVE WASTE DISPOSAL
513
-------
best procedure is to store the wastes for several years at the reprocessing
plant to permit decay of the short half-life radioisotopes. This reduces
the heat-generation rate and radiation hazard during shipment and storage
in the permanent facilities. The wastes may be temporarily stored as
either liquid solutions or solidified wastes at the reprocessing plant
site; the choice depending on the physical form of the wastes when dis-
charged from the fuel separations process.
In this study the wastes are assumed to be stored for five years (about
the optimum period) before shipment to the mines. The wastes are encap-
sulated before shipment, and arc stored in the permanent facility without
removal from the capsules or treatment.
The low level activity wastes include only materials received from private
nuclear industry In the areas of feed materials conversion, fuel fabrica-
tion, and reactor operations. All v;astes are received ready to bury. It
excludes materials from the uranium mills and mines. This activity in-
cludes only radioactive materials permanently buried at commercial surface
burial waste sites. It does not include materials sent to deep burial
sites or materials buried near the surface at other sites. This account
does not include samples, failed equipment, etc., shipped from production
plants to research facilities or government bodies for analyses and investi-
gations of equipment performance.
The high level activity wastes include only materials expected to be
placed in permanent engineered storage and all wastes are received ready
for storage. The material buried consists only of highly radioactive
materials, primarily fission products, from fuel reprocessing plants.
^nvironmcntal Jmpact.
Environmental impacts in disposing of radioactive waste involves only
land use. There is no escape of radioactive materials from the burial
sites to the air or adjacent water tables. The amount of material to be
handled and its activity for each of the years 1975, 1980, 1985, and ]990
are given in Table V-41.
TABLE V-41. SUMMARY OF RADIOACTIVE WASTE
1975 1980 1985 1990
Amount, cu ft l.SxlO6 2.9xl06 5xlO& lOxlO6
Activity, curies 5.7xl06 1.3x10$ 3.4xl09 5.5xl09
514
-------
Transportation in the Nuclear Industry
Transportation of various materials is required to link the various steps
indicated in Figure V-l which is in the Technical Approach Section of this
report. A process flowsheet for transportation is given in Figure V-15.
Railroads are the primary mode of transporting nuclear materials in the
nuclear power industry ^7ith shipments by truck being the secondary mode.
The principal means of water transportation would be transcontinental
freighter. In some steps of the process, the shipments would not go off-
site.
The quantities of nuclear materials that will be shipped in the years 1975,
1980, 1985, and 1990 are given in Table V-42. The industrial chemical
shipments needed to support the processes are not included. In general,
except for accidents, the impacts of shipments of nuclear materials is
identical to transportation of any other material. The usual require-
ments for use of right-of-way, energy consumption, and capital equipment
acquisitions have their normal impact on the environment. The impact of
accidents has not been evaluated since this would require a statistical
analysis of the frequency and severity of accidents for similar types of
materials. All nuclear materials are in innocuous form or arc packaged
to minimize loss of control of the material in the event of an accident.
Thus, the cleanup after an accident presents no greater problem than any
other industrial chemical shipment.
The AEG and others are currently conducting statistical evaluations of the
frequency and severity of accidents and the attendant risk for shipments
of spent fuel, recovered plutonium, and wastes. If we assume an accident,
the following is a ranking of materials from the most hazardous, if prompt
and effective cleanup steps are not taken.
Material Being Shipped
0 Plutonium
e Spent Fuel
o Wastes
0 UF6
0 Fuel Elements
0 U03
o
0 Thorium Ore
515
-------
Extraction
Ul
Extraction
locale
Pre-Ut1l1rst1on
Prccesslnc
Australia
Continental U.S.
South Africa
South Ar.erlca
USSR
of
Mods
•Korenelature
R.T.W are Rail. Truekt toter Transportation and 0 1s c-.-s1te.
Post-Utilisation
Processing
Liquid Ketal
Fast Reactor
H1ch Tempera ture
as Cooled Rctctcr
FIGURE V-15. NUCLEAR (FISSION) FUEL CYCLE PROCESS FLOWSHEET
-------
TABLE V-42. NUCLEAR MATERIAL SHIPMENTS
(Toes)
Material
Uranium Ore
Thorium Ore (Reactor use)
U3°8
ThO, (Reactor use
C
UFg to enrichment-natural
-Recovered
UF, to fabrication
0
Fuel Elements - LWR .
- HTGR
- LKFBR
Spent Fuel - LWR
- HTGR
- LMFBR
UO, - Recovered uranium
Plutonium
Waste
• 1975
9.Sxl06
180
ISxlO3
7
23x1 03
1900
4450
5100
40
2000
1500
3
T.SxlO6 cu. ft.
1930
16x106
6700
31xl03
270
39x1 O3
5000
6650
8900
3100
5
5600
5
4000
31
2.9xl06 cu. ft.
1935 .
23x1 O6
25x1 O3
53-<103
1000
67x1 O3
8100
13300
ISxlO3
gxlO3
12
9x1 03
12
6600
63
5x1 O6 cu. ft.
1990
44x1 O6
52x1 O3
84x1 O3
2100
105x103
ISxlO3
21x103
23x1 O3
2ixl03
2600
17xl03
9400
SCO
12xl03
150
lOxlO6 cu. ft.
Net weight of material indicated does not include container, shielding, or protective
packaging which in the case of spent fusl and plutonium is of the order of 50 tines '
the weight of the material and must make the return trip enipty.
-------
s> Uranium Ore
This ranking is based upon the relative toxicity and chemical stability of
the compounds and makes no judgment regarding the effectiveness of the con-
tainer or shipping regulations. The fuel elements are ranked above 1103
since they may contain pLutoniuin, and below UFg because of their chemical
and physical stability.
We have assumed that no releases occur during the transport of nuclear
materials between process steps of the fuel cycle simply because we have
assumed normal operational conditions. Therefore, control mechanisms and
associated costs were not studied.
References
V-l. BNWL-B-141, "Data for Preliminary Demonstration Phase of the Environ-
mental Quality Information and Planning System (EQUIPS)", Battelle,
Pacific Northwest Laboratory,- December, 1971.
V-2, R. L. Engel, "DAEDALUS II: A Computer Code to Generate a Linear
Programming Model of a Nuclear Power Economy", BNWL-1459, June, 1970.
V-3, USAEC Division of Reactor Development and Technology, "Potential
Nuclear Power Growth Patterns", WASH-109S, December, 1970.
V-4. D. E. Deonigi, R. W. McKec, and D. R. Haffner, "Isotope Production
and Availability From Power Reactors", BNUL-716, July, 1968.
V-5. Federal Power Commission Press Release No. 17372.
V-6. U.S. Energy Outlook, An Initial Appraisal 1971-1985, An Interim
Report of the National Petroleum Council, Volume One, July, 1971.
V-7. USAEC Division of Operations Analysis and Forecasting, Forecast of
Growth of Nuclear Power, UASH-1139, January, 1971.
V-8. "Preliminary Program International Conference on Nuclear Solutions
to World Energy Problems", American Nuclear Society Winter Meeting,
November 12-17, 1972, Washington, D.C., Supplement to Nuclear News,
pp 99-108, Spetember, 1972.
V-9. An Assessment of the Economic Effects of Radiation Exposure Stan-
dards For Uranium Mirers, Report to Federal Radiation Council,
Arthur D. Little, Inc., September, 1970.
V-10. J. B. Burnham, L. G. Merker, and D. E. Deonigi, "Comparative Costs
of Oxide Fuel Elements", Vols. 1, 2, and 3 and Appendix, BNUL-273,
July, 1966.
V-ll. ASA Subcommittee N5.2, "Current Practices in the Handling and
Storage of Wastes From Nuclear Fuel Fabrication Operations, Novem-
ber, 1966.
518
-------
V-12. D. H. Leo and S. Jaye, "High Temperatute Gas-Cooled Reactor Fuel
Costs Today and Tomorrow", Gulf General Atomic Document, GA-10730,
September 1, 1971.
V-13. Unpublished data.
V-14. Reference Safety Analysis Report (RESAR), Rev. 1, Westinghouse.
V-15. Verplank Nuclear Power Station Safety Analysis Report.
V-16. Fort St. Vrain Power Station Safety Analysis Report, Public Service
Company of Colorado.
V-17. J. 0. .Blomeke, F. E. Harrington, Management of Radioactive Wastes
of Nuclear Power Stations, ORNL-4070, January, 1968.
V-18. R. C. DeLozier, L. D. Reynolds, and H. I. Baucrs, Concept -
Computerized Conceptual Cost Estimates for Ster.m Electric Power
Plants - Phase 1: User's Manual, ORNL-TM-3276 (October, 1971).
V-19. K. R. Wise and B. M. Cole, "A Survey of Heat Sink Capacity of Major
Streams Within the U.S.", BNWL-951, Battelle-Northwest, 1969.
V-20. %E. R. Irish and W. H. Rcas, The Purex Process - A Solvent
Extraction Reprocessing Method for Irradiated Uranium, HW-49483A,
1957.
V-21. Siting of Fuel Reprocessing Plants and Waste Management Facilities,
ORNL-4451, 1970.
V-22. Nuclear Fuel Services, Inc., Safety Analysis Report, AEC Docket No.
50-201.
V-23. R. E. Adams, R. D. Ackely, and W. E. Brovming, Jr., "Removal of
Radioactive Methyl Iodide From Steam-Air Systems", ORNL-4040,
1967,
V-24. G. H. Sykes and J. A. Harper, "Design and Operation of a Large Sand
Bed for Air Filtration", in Treatment of Airborne Radioactive Wastes
(Proceedings of a Symposium), CONF-680S11, 1968.
V-25. c. L. Bendixen and G. F. Offutt, Rare Gas Recovery Facility at the
Idaho Chemical Processing Plant, IN-1221, April 1969.
V-26. J. R. Merriman, J. H. Pashley, K. c. Habiger, M. J. Stevenson, and
L. W. Anderson, "Concentration and Collection of Krypton and Xenon
by Selective-Absorption in Fluorocarbon Solvents", in Treatment of
Airborne Radioactive Wastes (Proceedings of a Symposium), COHF-
680811, 1968.
519
-------
V-27. N, D, Dudey, "Review of Low-Mass Atom Productipn in Fast Reactors",
ANL-7434, 1968.
V-28. W. A. Hansy, "Fission-Product Tritium in Fuel-Processing Waste",
Nucl. Safety 5 (4), pp 339-403, 1964.
V-29. J. 0. Biomekc, "Management of Fission Product Tritium in Fuel
Processing Wastes", ORNL-TM-851, May, 1964.
V-30. J. H. Goode, "Hot-Cell Evaluation of the Release of Tritium and
85Krypton During Processing of ThO^-UOo Fuels", ORNL-3956, June,
1966.
V-31. J. II. Gcode and V.C.A. Vaughen, ''ORNL Experiments on the Behavior
of Tritium During Head-End Processing of Irradiated Reactor Fuels",
ORNL-TM-2793, February, 1970.
V-32. D. G. Jacobs, "Sources of Tritium and Its Behavior Upon Release to
the Environment", TID-24635, 1968.
V-33. J. 0. Blomeke, et al., "Estimated Costs of High-Levcl Waste Manage-
ment", Proceeding!; of the Symposium on the Solidification and
Storage of High Level Radioactive Wastes, CONF-600208, 1966.
V-34. J. 0. McElroy, et al., "Waste Solidification Program Summary
Report", Volume II, BNWL-1667, 1972.
520
-------
APPENDIX W
ADVANCED ENERGY SYSTEMS
Table of Contents
Sunimary 523
Fuel Cell Energy Systems 526
Solar Energy Systems 531
Heat Pumps .....'.. 540
Geothcrmal Power 542
Thermonuclear Fusion 553
Breeder Reactors 555
Tidal Power 566
Magnetohydrodynami.es 574
Thermionic Power 578
Thermoelectric 579
References 582
List of Tables
W-l. Environnental Ranking of Advanced Energy Systems. . . . 524
W-2. Estimated Funding Effort and Requirements Related
to Fuel Cells 530
W-3. Projected Program Costs and Schedule for Three
Options 538
W-4. Coefficients of Performance for Electrically Driven
Heat Pumps with Various Sources and Sinks 540
W-5. Burden of Environment 1,000 MW Geothertnal Plant .... 550
W-6. Proposed Geothermal Resources Research Program 552
W-7. Effectiveness and Economic Costs for Pollution Control
with Respect to Meeting Existing and Anticipated
Regulations 553
W-8. World Energy Reserves of "Infinite Fuels" 554
W-9. Prominent CTR Energy Cycles 555
W-10. Summary of Effluents 561
W-ll. D-Li Energy Cycle Effluents 1000 MWe, 40 Percent
Efficiency 563
W-12. Nuclear Fusion Costs (by Milestone) 563
W-13. Nuclear Fusion Costs by Year in Millions of 1971
Dollars 554
List of Figures
W-l. Power System Efficiency Comparison. . 528
W-2. Solar Energy Conversion Modes 532
521
-------
List of Figures (continued)
W-3. Conceptual Deuterium Tritium Fuel Cycle 557
W-4. Conceptual Design of an Inertial Confinement CTR
Power Plant 559
W-5. Conceptual Design of an Electro-Magnetic CTR Power
Plant 560
W-6. Simplified Power-Cycle Diagram, 1000 MWe GCFBR 567
W-7. Simplified Flow Diagram of MSBR System 570
W-8. Nuclear Steam-Supply Components in a Liquid-Metal-
Coolcd Breeder Reactor 572
522
-------
APPENDIX W
ADVANCED ENERGY SYSTEMS
Summary
The objective of this phase of the study was to identify potential ad-
vanced energy systems, to identify the environmental burdens, and to
rank the systems environmentally. ;
In order to rank the prospective energy systems environmentally, con-
sideration must be given to a wide range of factors. In many cases, it
is not possible to develop quantitative measures of the extent of envir-
onmental burden. More important, there is not yet available a method
for comparing emissions. For example, it is not possible to trade,
quantitatively, cooling water requirements for air pollutant emissions.
Thus, for present purposes it has been necessary to make qualitative
judgments of the relative significance of many environmental burdens.
Consideration has been given to cooling water requirements and emissions
of common air pollutants; land requirements for solar energy collectors
and for strip mining; to problems associated with a large variety of waste
products; to the potential for local or meso-scale climate modification;
and many others.
Each energy system was considered in terms of both real and potential
environmental burden. They were then grouped relative to each other into
four qualitative classes, from excellent to poor, to reflect increasing
environmental burden. Consideration was given not only to adverse factors;
any environmental gains were also considered. For example, breeder re-
actor systems were credited for negative fuel consumption; solid waste
utilization in steam electric plants received credit both for its contri-
bution to the reduction of solid waste disposal problems and for reducing
the need for virgin fuels.
Some of the systems can be considered to be rapidly emerging technology;
some of the environmental factors charged against them may be resolved
soon. In some cases, there is conflicting information as to the potential
burden. In most cases, the scientists and engineers who are closely
associated with a particular system tend to be very optimistic about the
potential of that sysLem to provide significant energy at relatively modest
environmental cost. Considerable effort was devoted to achieving a bal-
ance and avoiding excessive optimism or pessimism.
The rankings of the selected advanced energy systems arc presented in
Table W-l. Those considered capable of producing significant power in
the future arc identified.
523
-------
TABLE W-l. ENVIRONMENTAL RANKING OF ADVANCED ENERGY SYSTEMS
Excellent
Solar Energy (Residential)(c)
Heat Pumps (Residential, Electric)(
Conventional Hydroelectric'3'
Good
Tidal
Geothermal (Hydrocracked dry rock)^c'
Solar (Rankine cycle)(c)
Solar (Stirling)^
Geothermal (Natural)(>c'
Fusion
Solar (Satellite)
Solar (Photovoltaic)
Natural gas/steam/electric(
Fair
Geothermal (nuclear stimulated)
Magnetohydrodynamic (Closed cycle, nuclear)^ '
Breeder reactors (gas-cooled(c), liquid motal(c), and molten salt)
Fuel Cells (Coal-to-hydrogen gasification)(c)
Light Water Nuclear Reactors(a»b»c)
Fuel Cell (Nuclear-electrolytic hydrogen)'0'
Thermoelectric (Solar)
Gasified coal/steam/elcctric(c)
Solid Waste Utilization (Trash-coal/steam/electric)'b»c'
Magnetohydrodynamic (Open-cycle - coal/stcam/electric)(c/
Poor
Coal/Steam/Electric ^a^
Thermionic (Nuclear)
(a) The conventional systems in 1972 are included for reference pur-
poses only.
(b) Capable of producing significantly increased energy by 1975.
(c) Capable of producing significant energy by 1990.
524
-------
Much of the reasoning behind the relative positions assigned to the
various systems can be illustrated briefly as follows.
Fuel eel! systems have at least two advantages over conventional steam
electric systems; they are more efficient thermally and would produce
substantially less air pollution. These advantages may be illusory,
however, because the fuel production would represent an additional step
which would reduce overall efficiency. Moreover, if the fuel is produced
by gasifying fossil fuels, there would be some production of conventional
air pollutants.
The solar energy systems arc widely considered to be environmentally
"clean". However, the collectors would require the dedication of very
large land areas. Systems using satellite collectors would require beam
transmission of the energy to receivers on the ground. Some concern has
been expressed for the potential hazard associated with the relative
intensity of the proposed beam of electromagnetic radiation.
Residential heat pumps represent largely beneficial environmental impact
because they would reduce the load on central power plants. On the other
hand, there would be a requirement for supplementary space heating at
times for which resistance heating systems appear attractive. In that
ease, widespread use of heat pumps might lead to increased central power
station load, with attendant environmental insults, during the heating
season.
The various approaches suggested for utilizing geothermal energy are all
site limited, and all appear to require dedication of substantial amounts
of land, much of which is presently scenic. In addition, there is a
potential for the contamination of surface water with dissolved salts,
and for air pollution with hydrogen sulfide or ammonia, for example.
Concern has also been expressed over possible subsidence of relatively
large areas, and for possible seismic activity as a result of deep well
injection.
.Controlled Thermonuclear Fusion reactors have several potential advantages
over fission reactors and fossil-fueled plants. They should be more
efficient, thus requiring less cooling capacity; there will be no combus-
tion products; and radioactive wastes will be largely contained. How-
ever, there will be substantial tritium production, and the reactor
structures will be radioactive.
Utilization of tidal currents to produce electricity is attractive as a
nonpolluting system. However, there are several environmental factors,
including alteration of estuaries, both physically and biologically, and
the potential for local or mcso-scale alteration of weather and climate.
Solid waste combustion in thermal electric plants has already been men-
tioned for its overall beneficial environmental effects. A system util-
izing solid waste would produce similar air pollution except appreciably
525
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reduced sulfur emissions and possibly increased heat rejection problems
as compared to a conventional coal-fired plant.
Breeder reactors as a group have similarly been mentioned as having a
decided environmental advantage because of their fuel production as
opposed to consumption. However, their thermal efficiency is not al-
together favorable, and their production of tritium and fission products
which must be stored for decay represent adverse environmental factors.
In addition, the shipment and reprocessing of fuel in large quantities
represents a certain environmental risk because of the possibility of
accidents.
MaRnctohydrodynamic power systems have received much favorable attention
largely because of their relatively high thermal efficiency. Seed re-
covery must be thorough for economic as well as environmental reasons,
but it is not known how important might be the escape of relatively small
amounts, by weight, of very small diameter seed particles which are
extremely difficult to capture. Sulfur recovery within the system is a
decided bonus but the very high temperatures associated with MUD will tend
to cnchance production of oxides of nitrogen.
Therrooe1ectrIc and thermionic systems are not expected to provide any
significant power to meet national demands by 1990 or beyond.
The more complete detailed descriptions of the selected advanced energy
systems are presented in the following section. It should be recognized
that the order in which they are presented is not necessarily the order
of environmental ranking nor energy potential which is presented in
Table W-l.
Fuel Cell Energy Systems
A fuel cell is an electrochemical energy conversion device that can con-
tinuously produce electrical energy from an input of chemical fuel and
oxidizer. The fuel cell is not limited as Carnot cycle systems and theo-
retically can achieve higher energy efficiency. However, high capital
costs prevent fuel cells use for large-scale central station power gener-
ation. Fuel cell power plants are more competitive in smaller sizes
(<50 1-M) for dispersed power generation. The problems of conversion of
DC as generated in the fuel cell to AC as used universally at present must
also be considered along with the costs of such conversion when it is
required.
Fuel cells can be roughly classified by type of electrolyte:
Aqueous electrolytes: temperature range, 0-200 C
Molten salt electrolytes: temperature range, 500-700 C
Solid electrolytes: temperature range above 700 C
526
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The lower temperature aqueous electrolyte type fuel cells hold the most
promise for the future. Oxygen in the air is used as the oxidizer and
hydrocarbons and hydrogen are the principal fuels of interest.
Four specific fuel cell systems of interest are described here, together
with an appraisal of their acceptability.
System 1.
Natural gas distributed by pipeiiiie is the fuel and oxygen in the air is
the oxidizer. The fuel cell power plant consists of three subsystems:
(1) a steam reformer to convert methane to hydrogen and carbon dioxide,
(2) the fuel cell stacks, and (3) a DC to AC inverter. There are several
possible applications beiiig studied that can be grouped according to size
and location:
System 1A 12-50 kw Residential/commercial
System IB 10-20 MW Substation
System 1C 100 KW Central station.
System 1A. This has been the subject of the $50 million TARGET program of
Pratt & Whitney Aircraft (P&WA) and the gas utility industry, begun in
1967, and now in the second phase of field test.^ ' The principal
limitation has been capital cost which has been decreased from about
$1500/kw in 1968 to about $400/kw in 1972 with forecasts cf $200 to
$250/kw during commercial production (Phase 3). Because of the dependence
on natural gas, it is unlikely that this system will find wide application
before the 1980's when coal gasification will provide a reliable supply
of synthetic gas (methane).
System IB. This is similar to System 1A and is the subject of current
studies for the electric utility industry(w~2) to realize the advantages
of dispersed siting on the electric power network (electric transmission
savings) for either base load or peaking duty with estimated installed
costs of $140 to $165/kw and $110 to $135/kw, respectively. For sub-
station use, versatility in operation on other fuels is required in
addition to natural gas, such as, propane and low-sulfur liquid fuels.
Estimates of cost goals indicate that to be competitive with nuclear
energy, fuel cell fuel costs would have to be below $0.80/10^ Btu; to be
competitive with gas turbines fuel cost could be in the range of $0.80
to $1.10/10 Btu. Whether the system's goals can be achieved will be
determined by about 1976 with potential use by 1980. Near-term use is
limited by supply of natural gas and low sulfur liquid fuels; long-range
use is dependent on development of synthetic gas (methane) by coal gasi-
fication in the 1980's.
System 1C. Use of fuel cells for large-scale central station power gener-
ation does not appear promising with present fuels or future synthetic
fuels because the efficiency advantage of fuel cells over steam and gas
turbine systems decreases as power output increases to 100 MW and larger
(sec Figure W-l). Also a principal savings for fuel cells is in dispersed
527
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use with pipeline transmission of gas energy where credit for savings over
electric transmission can be -realized.
System 2 -
Hydrogen gas produced from coal and distributed by pipeline is the fuel
and oxygen in the air as the oxidizer. The fuel cell power plant is
simpler and lower cost than System 1 since ah integral reformer is not
needed. . For use of pipeline hydrogen, it is questionable that fuel cells
could be^dispersed to the single residence level. Thus, the urban energy
system currently under study by Battelle at about the 1 1-Itf level appears
optimum for safety while retaining most of the economic and esthetic
advantages of underground gas transmission as opposed to. overhead electri-
cal transmission and retaining the option for utilization of waste heat.
fry_s tetn ^3
Nuclear energy (fission or fusion) can be the primary energy source to pro-
duce low cost electrical energy which is used to produce hydrogen by water
electrolysis (other schemes for direct production of hydrogen from v/ater
by nuclear energy are presently remote possibilities). Hydrogen then be-
comes the energy carrier via underground pipelines for dispersed utilisa-
tion of fuel cells at urban load centers as in System 2.
System 4
Solar energy can bo used directly as the primary energy source to produce
electricity (by thermal or photovoltaic means) which is used to produce
hydrogen by water electrolysis. Hydrogen then becomes the energy carrier
via underground pipelines for dispersed utilization of fuel cells at
urban load centers as in System 2.
Potential Environmental Burden of Fuel Cells
_g vs. tern 1. - Integral Reformer (Natural Gas, Oil). Reduced waste heat
rejection is possible with System 1 because of higher thermal efficiency
of fuel cells compared to conventional energy converters. As a first
approximation, the improvement in fuel utilization for fuel cells can be
estimated from efficiency versus power output shown below.
DO
40
EFFICIENCY
rcnccNT 30
10
met ecu SYM
0' t_l,.UUIU 1 I I I III- 1 1 11IUII |_1J .,!.,._ .,,.„;.,
' 13 IOO 1.OOO. 10.OOO 1OO.COO
POWER 0'JTPUT - C.ILOWATTS
FIGURE W-l. POWER SYSTEM EFFICIENCY COMPARISON^'2)
528
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Fuel cells have reduced atmospheric pollution emissions'compared to most
combustion systems. Fuel cells with integral reformers have integral
scrubbers to remove sulfur dioxides. Principal source of atmospheric
contaminants is the fuel burned to supply heat to reformer. Significant
reduction of atmospheric pollutants is achieved with fuel cells compared
to gas-fired central station as shown in the following tabulation:
Pounds per Thousand kwhr
Gas-Fired Fuel
Central Station Cells(a)
Sulfur Dioxide 0.3 0.0003
Nitrogen Oxides 4 0.24 •
Hydrocarbons 2.8 0.23
Participates 0.1 0.00003
(a) Based on data from experimental fuel cells
Source: Reference W-2
Since fuel cells do not require a heat sink as do Carnot cycle systems,
the heat load represented by the inefficiency is added to the atmosphere
(air cooling used) rather than water, and heat dissipation is as dis-
persed as the fuel cell power plants. Some heat can be beneficially used
at residential/commercial sites.
The use of dispersed fuel cells results in a proportionate reduction of
overhead electrical transmission requirements with improvement of land use
and esthetic benefit.
The use of fuel cells on pipeline gas can be arranged to provide energy
storage for peak use periods and reduce requirements for other peak load
systems such as: conventional fossil fueled peaking systems, use of
marginal fossil-fueled base-load systems of high pollution level, and
pumped-hydro storage.
Future use of coal gasification to provide a (high Btu) synthetic gas for
pipeline distribution wil add to the atmospheric pollution load at the
coal gasification site while removing sulfur and reducing the sulfur
oxide atmospheric pollution .it the fuel cell site.
System 2. Pipeline Hydrogen (Fron Coal). The use of pipeline hydrogen
will eliminate atmospheric pollution load at fuel cell sites compared to
System 1. Coal gasification will provide some .atmospheric pollutants but
probably no significant NOX if carried out at low enough temperature.
Sulfur and other atmospheric contaminant control will be greatly reduced
by economy of large-scale pollution control and will only be produced at
cites remote from urban areas.
System 3. Nuclear Energy (Hvdrogen bv Electrolysis). Local atmospheric
pollution will be completely eliminated, compared to Systems 1 and 2, by
use of electrolysis of water as the source of hydrogen (rather than coal).
529
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There will be an increased thermal pollution load at trhe nuclear/electric
generating site due to the inefficiency of water electrolysis and greater
need for electric power. Present state-of-the-art water electrolysis is
less than 50 percent efficient. Advanced water electrolysis cells are
expected to increase the efficiency to -75 percent, and long-range goals
would be an efficiency of 80 to 90 percent. It should be noted that
theoretical electrical energy (voltage) efficiencies of water electroly-
sis and fuel cell arc 100 percent. Theoretical thermal efficiency of hy-
drogen production by electrolysis is about 120 percent but corresponding
theoretical thermal efficiency of l^/C^ fuel cell about 82 percent.
With hydrogen generation using nuclear/electric source and pipeline dis-
tribution of hydrogen, remote siting of the nuclear plant is possible.
Energy distribution by pipeline hydrogen is more economical than under-
ground electrical distribution in general and more economical than high
voltage overhead electrical transmission for distance greater than 400
miles.
Systemi 4. Solar Energy (Hydrogen by Electrolysis). An inefficiency in
hydrogen generation by water electrolysis using a solar/electric energy
source does not add materially to the thermal burden of the earth.
This is an ideal system in that there is no atmospheric pollution, no
thermal pollution, and no overhead transmission lines. Hydrogen provides
a means of underground energy storage for peak power demand and would
eliminate the need for pumped hydro sites,
Estimated Funding Effort and Requirements
Estimated funding requirements for research and development related to
fuel cells are given in Table W-2.
TABLE.W-2. ESTIMATED FUNDING EFFORT AND REQUIREMENTS RELATED
TO FUEL CELLS (Millions of Dollars)
Millions of Dollars
Expenditures Expenditure for Each 5-Year Period Through
to Date, Beyond
System 1972 1975 1980 1985 . 1990 . 1990
1, N 5000
2(c) 5000
3 and 4(c) 2
26 (b)
3(d)
3
15 21 lo(b)
5 . . 25 / »
5(e) 9(e)
?
25(3)
12(e)
?
9
?
(a) This is estimated past expenditures on TARGET program and related fuel
cell research. Does not include ^-$250,000,000-of prior government R&D
530
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related to developing Apollo and Gemini fuel cells.
(b) Estimated funding by electric utilities to evaluate fuel cells for
substation use.
(c) System 2 costs do not include funding on coal gasification or
production of hydrogen from coal.
(d) Estimated expenditure to develop urban fuel cell concept and re-
lated hydrogen transmission technology, and to explore residential
d-c usage and waste heat utilization.
(e) Estimated expenditure to develop water electrolysis as an'economic
alternative to hydrogen production from fossil fuels by use of
nuclear and/or solar energy.
Magnitude of Energy That Can Be Developed
For System 1, the magnitude of the energy that can be developed using a
fuel cell system is limited by the present availability of natural gas
that can be directed from other uses to this form of electric energy
production. The use of low sulfur liquid fuels presents a similar short
term supply situation.
Successful development of economic coal gasification would permit a high
percentage of electric needs to be satisfied by fuel cells using either
synthetic methane or hydrogen for System 2.
Systems 3 and 4 are predicated on reduction in cost of electric power
by fission, fusion, or solar means to near or less than the cost of
hydrogen produced from coal. All electric energy needs beyond the year
2000 could ultimately be provided by a hydrogen distribution system with
dispersed urban fuel cells. Also, with low cost hydrogen, residential,
commercial, and industrial thermal energy requirements could be satisfied
by pipeline hydrogen as well as the needs of the chemical and metallurgical
industries for hydrogen (i.e., ammonia and iron ore reduction).
Solar Energy Systems
Several types of systems for converting solar energy to electrical energy
are theoretically feasible for large-scale central power station use.
These will be discussed below. It should be kept in mind that residential
healing and cooling consumes nearly one-fourth of the fuel required for the
United States and that solar energy could best provide a substantial portion
of these requirements "on site" to reduce the overall central power station
requirements. (W-3.V7-4)
Figure W-2 is a diagram showing various solar energy conversion modes pre-
sently available with expected efficiencies indicated.'k~^' Not shown on
531
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PHOTOVOLTAIC
CONVERTER
01
u>
N>
10% (20%)
STATIC
CONCENTRATOR
THERMOELECTRIC
CONVERTER
0% (20%)
SOLATt RADIATION
CONCENTRATOR
THERMIONIC
CONVERTER
10% (25)4)
LLECTRIC
POWER
( ) EXPECTED FUTURE EFFICIENCY
DYNAMIC
COLLECTOR
VAPOR CYCLE
CONVERTERS
25% (40%)
GENERATOR
THERMAL
COLLECTOR
HEATER
4C%
T
r
HOT GAS
HOTLIQUID
FIGURE W-2. SOLAR ENERGY CONVERSION MODES
-------
this figure is the simole scheme that has existed since1the creation of
the world, which is using solar energy to grow trees to provide fuel for
conventional power plants. Ov"3)
If one considers the average daily radiation for the continental United
States, it is realized that the energy level is quite low. Therefore,
large collector areas are required to capture enough energy to power a
large electrical generating station, For example, the average daily
amount of total solar radiation (direct and diffuse) incident on a
horizontal surface in the continental United States is about 600
Langley's/day (2,210 Btu/ft -day, or 27 watts/ft2) in June and decreases
to about 200 Langley1s/day (740 Etu/ft2-day. or 9 watts/ft2) in De-
cember.' ' Thus, if a horizontal flat plate collector and -associated
equipment were 100 percent efficient in converting this solar energy to
electricity, a 1,000 MW station would require a collector area of
approximately 1.3 square miles in June, and 4.0 square miles in December.
Focusing collectors which track the sun will level out this yearly
variation in radiation intensity. The direct-normal intensity at 40
degrees north latitude will always average about 290 Btu/hr-ft at noon
on clear days, but the hours of sunlight will vary from about 15 hours
on June 21 to only about 9 hours on December 21.(w"7) Therefore, the
total flux received on a surface kept normal to the sunlight will vary
from about 3,200 Btu/ft2-day (39 watts/ft2) in June to about 2,000 Btu/
ft2-day (24 watts/ft ) in December. Consequently, a 1,000 MW generating
station, using sunlight-tracking collectors and operating at 100 percent
conversion efficiency, would require a collector area of approximately
1.3 square miles in June and 4.0 square miles in December.
Another consideration influencing the design of solar collectors is the
maximum operating temperature required by the energy conversion system.
The following tabulation outlines the basic requirements.' ' ' The use
of surface coatings to increase the ratio of solar energy absorbed to
the thermal radiation emitted will tend to increase the maximum tempera-
tures achieved for each type of collector and increase the collection
efficiency.
Maximum Operating Temperature Type Collector
Below 100 C (212 F) Stationary, nonfocusing
100 C (212 F) to 200 C (392 F) Stationary, focusing, low
concentration
Above 200 C (392 F) Tracking, focusing
Considering the overall technological and economical feasibility of the
various solar energy conversion systems discussed herein, they are rated
below in descending order of priority in terms of energy capability:
1. Residential heating, cooling, and hot water
2. Rankine cycle
533
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3. Solar cells.
4. Stirling engines.
5. Satellite system.
ResidentialHeating and Cooling
It has been reported that about 25 percent of the total energy con-
sumption in the United States is for the heating and cooling of build-
ings, and that 22 percent of the total is consumed for residential
dwellings. v«~3) QJJ the energy required for homes, an average all-
electric home in the United States consumes about 100 million Btu's
(29,300 Icwhr) per year, of which 45 percent is for heating, 15 percent
for cooling, and 25 percent for hot water.' "' Thus, if solar energy
were used to provide for the residential heating, cooling, and hot
water needs, this would represent a total energy savings of almost 20
percent.
Solar energy is already well distributed, and its quantity is quite well
matched Lo residential needs for comfort heating, cooling, and hot water.
For example, the average total amount of solar radiation (direct and
diffuse) falling on 1,000 square feet of horizontal surface in the United
States is approximately 550 million Btu's per year. However, energy
storage requirements, and winter and summer needs would have to be consi-
dered carefully for each locality, we well as optimum sloping of the roof
collectors for year-round use.
Perhaps it may never be feasible to provide for 100 percent of residential
heating and cooling by means of on-site collection and storage of solar
energy. One analysis, which considered only solar heating, concluded
that it is most economical to design for only about 50 percent of the
total requirements in most area.s of the United States. (W"10)
Enviromr.cntra 1 Factors. The successful development of "on-site" solar
heating and cooling for residential dwellings could reduce the environ-
mental pollution caused by central power plants by as much as 10-to 20
percent. Since solar energy is already well distributed, the use of its
energy when and where it is received will have the least overall detri-
mental effect on the surrounding environs.
Capital Costs. Home heating with solar energy is estimated to be cost
competitive with electric resistance heating at $0.02/kwhr ($5.85/10 Btu)
for many parts of the United States.(W~3) However, solar collector and
heat storage systems have not yet been developed to the necessary dependa-
bility and economy required for widespread public use.
RM) Expenditures. A complete 10-year progi'am of research and development
for solar heating and cooling of dwellings has been formulated.(w"3) This
calls for a total expenditure of between $10 to $20 million over the 10-
year period.
534
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Solnr Povorcd Rankine Cycle
This type of system usually consists of solar concentrators to focus the
sunlight onto heat collector tubes. This heat is then transferred by
means of a circulating fluid to a heat storage unit. The stored heat
energy is used as needed to produce stcrm for a conventional steam
turbine generating plant.
At least two such designs are currently under study.(W-4) Aden Maine!
at the University of Arizona is designing a collector using Frcsnel lenses
to concentrate the solar flux 10 times and focus them onto stainless steel
or glass ceramic pipes. These pipes would have selective coatings to
increase the relative absorptance of the solar energy, and would be en-
closed in evacuated glass tubes to further reduce heat losses. Nitrogen
gas would be circulated through the pipes and transfer the heat to a
central heat storage system consisting of an eutectic mixture of molten
salts. This stored heat would then be used to produce steam for a conven-
tional turbine as required.
The second study, headed by Ernst Eckert at the University of Minnesota
and Roger Schmidt at Minneapolis-Honeywell, Inc., utilizes a parabolic
reflector to concentrate the sunlight onto a heat pipe. Again, selective
coatings and evacuated chambers would be used to increase the collection
efficiency. Each heat pipe would have a separate heat storage unit
and the steam generated would be returned to the turbine-generator.
Work on solar-powered vapor turbines has been conducted by H. Tabor,
and a 6GO-\?att experimental unit has been built using dichlorobcnzene
as a working fluid.(W-8.W-11)
Another type of solar-powered Rankine cycle would use the thermal gra-
dients in the oceans to opnrate a turbine-generator unit.(W"12,W-13)
However, the overall temperature difference available is quite low (about
40 F) and, consequently, the overall thermal efficiency of the plant will
be very low, probably less than 5 percent. Therefore, very large heat
exchanger surface areas are required. If these heat exchangers can be
designed for low cost by proper design, and if efficient components are
developed, then this scheme may prove useful for some coastal regions
where favorable temperature gradients exist in the ocean.
Environmental Factors. Although solar energy has probably the fewest
potential environmental problems associated with its use of any of the
major sources of energy, some problems do exist. Collecting surfaces
absorb more sunlight than the earth does, and while this is not likely
to alter the local thermal balance in household or other small-scale use,
the large expanse of collecting surface required for a central power
plant might. For example, at an estimated maximum overall efficiency of
20 percent, a 1,000 MW solar-powered generating station would require a
collector surface area of approximately 12 square miles, assuming an
average daily intensity of 15 watts per square foot on a year-round
basis. However, a solar plant may have to be sized for winter radiation
535
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conditions, which could increase the collector size by 50 percent.
Thermal pollution will also be a problem if water-cooled steam con-
densers are used—even more so than with nuclear power plants because
solar installations are expected to have even lower thermal efficiencies.
If waste heat is returned to the atmosphere, it could help to restore the
local thermal balance. The effects of these changes in the thermal bal-
ance would depend on the local meteorological conditions, but are expected
to be small.
A floating power plant operating on the thermal gradients in the ocean
would have almost no detrimental environmental impact. It may present
some hazard to ships, and it would have to be designed to remain opera-
tional during severe storm conditions.
.Capj tal Costs. It is estimated that the cost of solar-thermal plants will
be not more than two or three times what fossil-fueled plants (less than
$500/kw) or nuclear-genera ting plants cost now, and that rising fuel costs
will eventually tip the balance in favor of solar-thermal plants whose
fuel is "free".(W-4) Before accurate estimates of costs can be made, how-
ever, more detailed engineering studies and some additional researcli are
necessary. But Moinel believes that full-scale solar-thermal power plants
could be built as early as 1985 with an adequate research effort. Other
estimates are somewhat less optimistic, but a group of western utility
companies is considering the development of a small solar-powered facility
that could serve as a prototype for peak load applications.
The capital costs for a floating power plant were estimated by J. H.
Anderson, Jr.'""^) to be only $l66/kw, and the total cost of electricity
to be only $0.00285/kwhr. However, considerable research and development
work needs to be done on various components of this system to verify these
estimates.
Solar Cells
Arrays of solar cells have been developed for use in space applications
to generate electrical energy directly from sunlight. For terrestrial
applications their output is reduced approximately tenfoldrbecause of the
lower radiation intensities and the diurnal variations. In addition,
storage of the electrical energy would be required, as well as conversion
from d-c to a-c power.
Environmenta1 Fac t or s. Thermal pollution is essentially zero for solar
cell arrays, as the sunlight is converted directly to electrical energy.
However, large land areas will be required because of the low conversion
efficiencies (e.g., 6 to S percent presently, perhaps increasing to 20
percent eventually). The estimated direct current output for terres-
trial use is 1 watt per square foot (w"5) so that a 1,000 MW generating
station would require approximately 36 square miles of land area, or about
23,000 acres. There certainly will be an environmental impact of such a
"solar farm" due to thermal updrafts such as now exist over cities, and
536
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because the land itself becomes unproductive.
Capital Costs. The present cost of small solar arrays (10 to 100 kw)
using silicon cells is about $300,000 per kw. Projected estimates for
array sizes of 1 to 1,000 liW are $50,000 per kv and for 1,000 to 10,000
IN sizes are $5,000 per Kw. O^"5) Some very recent estimates of costs
of thin-film CdS cells, once fully developed for low cost mass production,
indicate the costs may ultimately be reduced to less than $l,000/kw.
However, the efficiency of these cells may be less than 6 percent.
R&D Expenditure's. More than $10 million have been expended thus far in
developing silicon solar cells for space applications. To develop solar
cell arrays sufficiently to supply a significant portion of the electri-
cal energy requirements of the United States by the year 2000, an expen-
diture approaching $300 million per year for six years may be required. ('•''"-
Table W-3 presents another projected research costs program for develop-
ing low-cost solar arrays as a first basic step toward achieving largo"
scale use of solar cells.' '
Solar-Powered Stirling Engines
Focusing parabolic solar collectors have been used to power small Stirling
hot-air engines' ' >N '' and these could be mass produced for large-
scale generation of electrical power. Ov?~18) ^ parabolic solar collector
6 feet in diameter could generate approximately 200 watts using a Stirling
engine, which is an overall energy conversion efficiency of about 8 per-
cent at peak radiation intensities.
Environmental Factors. Again, a large area of land would be required for
a large-scale generating plant because of the low conversion efficiency.
If many small individual units were used, then somewhat more land would
be required because of space needed around each unit. The land area re-
quired would probably match or exceed that listed tor solar cells, namely
36 square miles for a 1,000 HW station.
The thermal pollution problems would be similar to those discussed for
the Rankine Cycle systems, as waste heat must be dissipated either to
the ambient air or another heat sink.
Capi.ta 1 Cost s. It has been estimated that solar powered Stirling' engines
could produce electricity for about $500 per kw while the sun is shining,
viliich is about one-third of the total time."1' ' These costs were divi-
ded up as follows: $1 per square foot for the 6 foot diameter prarbolic
collector, and $15 each for the 200-watt Stirling engines which could be
mass-produced. The remainder of the costs would involve tracking systems,
maintenance, etc.
R&D Expenditures. Solar-powered Stirling engines are a proven concept in
principle, but some problems with seals and with lubricants over long
537
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TABLE V-3. PROJECTED PROGRAM COSTS AKD SCHEDULE FOR THREE OPTIONS
U)
00
~ OFTIOi"
. RSSOttCSS
. PKASS • " '
E?£ IMVS A
?reli-JLiiarjr design & fcislbility asscss-.cnt.
Ccn:cpfjal design of alternative approaches.
Identification of critical systCT, para-.eters.
Fiiasc \
Estibliia aysten feasibility & r.ost dcsirablo
a;;roac :es. Assessment of tc:?i-.ical ad\-anccs needed.
Crass cost ar.4 schedule projection. '
Rase 3
Preliminary dcsic^ of preferred systcn. Detail
assc:s*.:n* of rcquire:r:r.ts iTclvidlr.g resource,
eirufacluriis wl test rcqyircsents. Preliminary
:y:tca :ost 6 r.chcduVo prajcctio.n. All pre-cccsl-t-
rcr.t objccti-rts csrpletcd.
Phase C
Firal definition: Frcesirs of concepts, approaches,
dcilgr.s, schcd-jic:, ari costs of pre£r
-------
time periods arc yet to be solved. Also, optimization studies would be
needed before arriving at a final design for large-scale power plants.
An expenditure of several million dollars per year for 10 years would
probably be required to develop such a system.
Satellite Solar Collection System
This scheme involves the putting of at lenst two giant satellite systems
into synchronous orbits with large arrays of solar cells to intercept
the solar energy. This energy mil then be converted to microwave radia-
tion, and beamed to earth receivers where it. could be reconverted to
electrical energy.(W"19,K-20)
One such satellite solar power station designed to produce 10,000 MW
would have a solar collector array area of 25 square miles, a microwave
transmitting antenna area of 1 sauaro mile, and an earth-based receiving
antenna area of 36 square miles.(W-20)
Environmental Fat-tors. The major impact of this arrangement would be the
possible hazard of the energy beam transmitted to earth. The intensities
may be high enough to cause seme damage to objects or living beings.
Safety measures would have to be devised to prevent entry into the beam.
Capital Costs. Cost estimates for this system have not been published,
but they will undoubtedly be very high. The costs given for solar cells
in another section will apply for the solar collector array. In addition,
there would be the cost of improving the technology for the microwave
transmitting and receiving equipment, as well as putting all of the
equipment into a synchronous orbit.
R&D Expenditures. It has been suggested that -the United States spend $500
million in the next 10 yearn to study the feasibility of a satellite solar
energy system.(W-21)
R&D costs for developing cheaper solar cells to be used in satellite sys-
tems are given in the solar cells section.
Other Systems
Other solar energy conversion systems include thermoelectric and thermionic
converters, and closed-cycle Brayton systems.
Thermoelectric and thermionic systems are described elsewhere in this re-
port, and solar concentrators would be used to provide the high surface
temperatures required. However, as yet, the overall efficiencies and
life expectancies are lovr, and the material costs arc high.
A closed-cycle Brayton (gas turbine) system could be operated using solar
collectors as a heat source, but its overall efficiency would be lower than
a comparable Rankine cycle because a gas compressor would be required in
539
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addition to a turbine expander. Also, larger heat exchangers would be
needed to compensate Cor lover heat transfer coefficients on the gas
side, as opposed to higher condensing and evaporating coefficients for
Rankine cycles,
Heat Pumps
The heat pump is a refrigeration system which can be used to provide both
heating and cooling. Heat pumps are also referred to as reverse-cycle
refrigeration, although this is somewhat of a misnomer since the basic
refrigeration cycle is still used. Heat pumps have primarily found
application in the comfort control of residential homes, although some
heat pumps have been installed in larger commercial buildings.
Although the heat pump could theoretically utilise any therirodynamic
cycle that produces refrigeration, economic considerations dictate that
the vapor compressions cycle bo used. The evaporator draws heat from a
low temperature source (the outdoor environment in the heating season and
the indoor environment in the cooling season) and this heat is rejected,
along with the heat of compression of the fluid, to the higher temperature
sink. • During the summer, heat is "pumped" to the outdoors and in the
whiter it is "pumped" indoors.
The most common measure of performance of the heat pump is the coefficient
of performance (C.O.P.), which is the ratio of the "useful" heat moved
to the quantity of energy required to operate the system. In the winter
season the useful heat is the energy rejected by the condenser. The
useful heat in the summer is the energy absorbed by the evaporator.
Table W~4 lists typical values of C.O.P.'s obtainable with various heat
sources and sinks.
TABLE W-4. COEFFICIENTS OF PERFORMANCE FOR
ELECTRICALLY DRIVEN HEAT PUMPS
WITH VARIOUS SOURCES AND SINKS
C.O.P.
Source/Sink Heating Cooling
Air
Water
Earth
2.5
5.0
3.0
3.0
4.0
3.0
540
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Environmental Burden
The widespread use of heat pumps for residential and commercial space
heating and cooling could substantially reduce the local air pollution
caused by the more conventional fossil-fuel fired heating systems since
the operation of these systems is essentially pollution free. The
electrical energy that is required is normally generated at a central
power plant where more sophisticated pollution control devices are avail-
able.
Heat pump systems can also conserve significant amounts of energy during
the heating season since a portion of the energy released to the heated
space is energy which vould not normally be tapped. This can be illus-
trated by considering the overall efficiency of utilization of fuel for
heating a home. For a typical gas- or oil-fired furnace, the efficiency
can be considered to be about 75 percent. For the case of the central
power station operating at 40 percent efficiency in conjunction with a
air-to-air heat pump operating with a C.O.P. of 2.5, the overall efficien-
cy can be calculated as 40 percent times 2.5 or 100 percent. This
represents a 33 percent increase over typical residential gas- or oil-
fired furnaces. Thus, the overall efficiency of utilisation of the fuel
is improved considerably. Supplemental resistance heating is sometimes
used in conjunction with residential heat pumps during the heating season.
Any extensive use of this supplemental heating system lowers the overall
energy efficiency and adversely accentuates the demand imposed on central
stations.
The environmental impact of using air as the heat source/sink is quite
small, but if water or earth is used as the source, the impact on the
environment must be assessed more carefully. If well water is used, the
water must be disposed of in a suitable manner, which usually means
drilling another well to return the heated or cooled water to the ground.
For earth heat sources, the changes brought about by continuously with-
drawing or adding heat from or to a finite mass of «;arth must be assessed.
Capital Costs
A three-ton heat pump unit installed in a typical residential home
( 1500 square feet) would cost about $1800. Operating costs of heating
a home with an electrically driven heat pump run appreciably higher than
the same house heated by natural gas, but about half as much as the same
house heated by electrical resistance heating.^
R&D Expendi turcs
Heat pump technology is well developed at the present time and commercially
available units have been on the market for some time. These units have
not found wide acceptance in the northern part of the country; however, due
to the fact that the C.O.P. of the, air-source heat pump drops off at
lower ambient temperatures. The use of solar energy as a heat source has
541
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received some attention. If suitable techniques for ^utilizing this energy
could be developed, the use of heat pumps would undoubtedly become more
widespread.
Ceothermal Power
System Description and Status
Geothermal power is the utilization of heat from the earth's interior to
produce electrical power and serve other useful purposes.
The present world utilization of energy from geothermal sources is about
1200 MW. While this represents an exceedingly small percentage of total
world and United States usage (about 0.1 percent in each case), geothcr.na!
power can be significant in its local utilization, e.g., California, Italy,
and New Zealand. The relative anticipated growth of geothermal power is
estimated to be 4000 MM by 1980, Approximately one-third of this growth
will occur in California, of which the majority will be in the Geysers
region.
In a recent article on geothermal energy Rexv^"22) estimated that by con-
certed exploration and development the proven geothermal resource could
be betwen 100,000 MW and 1,000,000 1E-I in the year 2000. Another(w~23)
estimate of the geothermal resource is 132,000 NW in 1985 and 395,000 1-!W
in 2000. By comparison, the present power capacity of the United States
is a little over 300,000 MW.
At the present time, any discussion of geothermal power1 must keep in mind
the distinctions between utilization, resource, and resource potential.
Thus, while present utilisation is small (about 1200 Ml'.') and proven re-
sources only a few times that, the known resource potential is significant-
ly larger. The utilization of this resource potential, both in the United
States and the world, will depend on technological development as well as
political and economic factors. Large-scale utilization of geothermal
power is unproven, but the tremendous resource potential as well as
advantages in economics, environmental pollution, and nondepletion make
it a highly attractive source for future energy needs.
Description of the Geothermal Energy System
In certain limited locations groundwater through pores and fissures in the
rock conies in contact with hot material rising from the earth's interior.
This results in locally large natural underground reservoirs of steam and/
or hot water which can be tapped by drilling to drive turbines in power
plants and provide space heating in buildings and greenhouses. These
geothermal energy sources can be described by
1. Natural steam systems.
(a) Dry steam fields which have a relatively high energy content
542
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(b) Wet steam fields which produce a mixture of hot water and
steam and have a lower energy content
2. Hot water fields which have a low energy content.
Fields of the first type can be used directly to produce electrical
energy from steam. It has been proposed that a heat exchanger using a
low boiling fluid such as freon be used to produce electricity in the
second type. The economics of this system have not been demonstrated
and may be unfavorable. This hot water source of energy can also be
used for local heating.
All types of geothermal resources are currently being used as sources of
energy. Dry'steam fields are generating about 700 MW of power at
Larderollo, Italy, and the Geysers, California. The Uairakei, New
Zealand, field produces about 200 MW of power from wet steam. At Cerro
Prieto, in Maja, California, a wet steam field is expected to start
producing 75 MW in January, 1973. Geothermal hot water is used for
residential heating in Oregon, Idaho, Iceland, and Siberia.
The identification of these geothermal resources has been based on surface
manifestations, e.g., hot springs and geysers. This is quite similar to
the early identification of oil reservoirs. As resource identification
techniques improve the extent and magnitude of the hot water or steam
geothermal resources are expected to increase significantly. This could
result in increased planning for the utilization of geothermal energy by
the nations' utilities companies.
Another, possibly more extensive, source of geothormal power is dry, hot
rock which does not have water associated with it. Means of tapping this
geothermal potential have not proved technically feasible, but field
experiments to test the concept have begun. Should this concept be
proven feasible, geothermal power could be used extansively.
A possible third geothermal energy source exists; the so-called geo-
pressure regions. Deep sedimentary basins filled with sand and clay or
shale of a young geologic age (such as exist off the U.S. Gulf Coast) are
generally undercompactcd to depths of several kilometers. The resultant
pores are filled with fluid. However, because of the undercompaction these
interstitial or pore fluids are at pressures between the hydrostatic and
lithostatic head. These regions are said to be gcopressurized.
The search for oil and gas throughout the world has discovered many geo-
pressure reservoirs. These have not been tapped for geothermal heat. The
location of many of them occurs in regions different from the steam and
hot water sources so that the geopressurc regions could potentially expand
the geothermal resource potential significantly.
Natural Steam Systems
As described above, the natural steam systems can be divided into dry and
543
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wet sources. The means of using dry geothermal steam to generate elec-
tric power is straightfon.'ard and is like the similar portion of a con-
ventional power plant except that the operating pressures and tempera-
tures are considerably lower. This requires turbines of special design.
•
Steam is available at the well head and is piped directly to the power
plant. The steam requires no special treatment other than filtering
out rock particles. The steam is expanded through a turbine, thereby
turning a conventional electric generator. The steam is discharged
through a condenser and converted into water. Because the dry steam
contains low impurities, the majority o£ the water can be evaporated
in cooling towers. A small amount of water containing concentrated
impurities must be dJsposcd of by surface means or by reinjection into
the ground.
In the case of wet steam sources steam must be separated from the water.
The hot water rising in the geothermal wells flashes to a mixture of
steam and water as the pressure decreases. The stcan and water are
separated outside the well head; the steam follows a cycle similar to
that described for the dry source. The water must be discharged into
the environment or rcjnjectcd into the ground. Because the water makes
up two-th'irds to four-fifths the fluid removed from the ground and
often carries a large dissolved mineral content, it poses serious en-
vironmental problems. Ceopressure systems may provide water hot enough
to flash into steam.
Hot Water Systems
In this proposed system, the hot water is pumped through a heat ex-
changer. Part of the energy would be transferred to a low boiling work-
ing fluid such as frcon and isobutane. The geothermal water, now
cooled, can be returned to the earth or disposed of in some other way.
The heat exchanger act.s as a boiler for the working fluid which is
evaporated and passed through a power turbine to generate electricity.
The fluid is then condensed and the working fluid is pumped to high
pressure and again run through the heat exchanger. This is -exactly
the fashion in which a conventional fossil-fired steam boiler or a
nuclear power plant operates. This type of system is also usable for
a pumped wet steam energy source.
Dry Rock Systems
The proposed dry rock system would utilize the energy from hot-dry
rocks close to the earth's surface. These are believed to be much more
widespread than the steam and hoc water sources. The approach would
be to drill a well deep into the hot rock. This rock is then frac-
tured by some means in order to provide a large volume whereby a work-
Ing fluid can be injected and heated. It has been proposed to fracture
the rock by conventional hydrofracturing techniques(w~24) or by nuclear
explosives.(W-25) Both approaches are unprovcn and speculative.
544
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The working fluid is injected into one drill hole and removed from an-
other drill hole spaced a considerable distance away. Depending on the
site location, temperature and pressure of the working fluid, and avail-
ability of local water, the power generating part of the cycle can be
any of the above discussed options or a suitable combination of them.
Potential Environmental Burden
Impact on the Land.
Land Use. The most obvious environmental effects associated with geo-
thermal power is the intrusion of an industrial operation into a usually
nonindustrial area. For example, a geothermal well is drilled in the
same fashion as an oil well. Problems include noise, the appearance of
drill rigs, access roadways, drill platform pads, drill cuttings, and
drill fluids. After the well is drilled it must be tested. This re-
sults in noise, wastewater, and probable air pollution. These are tem-
porary effects and can be minimized by careful planning. Once drilled
and in production the actual geothermal well can be made unobtrusive
and, hopefully, will offer no severe environmental problems.
Because the working fluid cannot be moved more than a mile without
serious heat loss, the generating plant must be located near the wells,
thereby localizing the total environmental impact to the site where the
geothermal field is located. The fluid is transported to the generating
plant by insulated pipes; these pipes are costly to run below ground;
therefore, the tendency will be to run them above ground. Such pipes
are visible environmental disturbances. The power and water plants are
conventional with noticeable noise level and cooling towers. The cool-
ing towers are large and evaporate steam into the atmosphere. Thus, a
residential usage would generally be incompatible with a geothermal
field.
Using the Geysers field as an example, present well-flow information in-
dicates that sufficient steam can be produced for a 1000 MM plant from
an area between 4 and 8 square miles. However, since only a small part
of the whole field is required for the wells, pipelines, and generat-
ing plants, the rest can be utilized for other purposes. For example,
at the Lardercllo field in Italy, where geothermal steam has been util-
ized for power production for nearly 60 years, an intensive agricultural
industry is carried on within the steam field, and many vineyards and
orchards are interspersed among the pipelines and wells. 0^-26)
The uses of the land associated with a geothermal field must be site de-
pendent, e.g., topography, climate, ground cover, etc. Many of the
known geothermal resource areas in the United States occur in places
that arc valued for their scenic beauty. Thus, the industrial character
of the geothermal area will notably affect the scenic values. The
evaluation of the environmental impact of a 520thermal field on the
land seems to be dependent on the viewpoint of the observer.(W-26,W-27)
545
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However, there seems to be general agreement that the'environmental
impact of a geothermal field is less than that of a correspondingly
sized nuclear or fossil fuel plant if one considers the total impact
of the mining, milling, fabrication, transportation, plant facilities,
fuel storage, and waste.
Subsidence. When large quantities of fluids are removed from an under-
ground reservoir, the land surface may sink. The consequences are
sometimes disastrous as was the case with the Wilmington, California,
oil field. Subsidence can occur when the reservoir rock is very porous;
removal of the fluid can cause the rock grains to fail or compact. If
the reservoir consists of fractured rock, subsidence is unlikely. The
ideal approach to utilization of the geothermal resource would be to re-
move fluid af or near its recharge rate, thus conserving the resource.
This approach would probably eliminate the subsidence problem. Since
subsidence could have serious environmental effects, but is not common,
future geothermal developments will have to be monitored for this
effect.
Seismic. Experience near Denver, Colorado, has indicated that seismic
activity can be stimulated by the injection of water deep underground.
The seismic effects of water withdrawal and reinjection in geothermal
fields will be peculiar to the particular area, and cannot be stated to
be or not to be a problem at this time. There are suggestions that the
induced nicroseisuiiri ty relieves strain on faults and tends to prevent
major earthquakes. 0'-'-28) However, because this seismic activity is not
predictable at the present time, it should be carefully monitored to in-
dicate possible hazards.
The seismic effects associated with nuclear stimulation of a dry geo-
themial resource is a different situation. While these effects are de-
pendent on the size of the device, depth of burial, geological struc-
ture, and location, it is highly unlikely that device sizes larger than
100 kilotons will be seismically acceptable for use at most locations.
Pollution Factors.
Thermal. In order for a thermal electric power plant to operate at
maximum efficiency, the steam must be condensed after passing through
the turbine. The amount of cold water required to condense the steam
in thermal plants is large. An efficient 1,000 MW fossil fuel plant
using cooling towers evaporates 15 to 25 million gallons of water a day,
whereas a nuclear power plant, because of its lower thermal efficiency,
evaporates about 50 percent more water. However, geothermal plants
that utilize dry steam do not require additional water for cooling.
The natural steam, after passing through the turbine, is condensed
wlthir the circulating cooling water and thus provides additional water
to the cooling towers. Thus, the dry stcan geothermal system should
pose little or no problem of thermal pollution to local water sources.
When the utilization of the geothermal resource is of the closed-cycle
546
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design, such as in the pressurized wet steam source or in the proposed
hot-dry rock source, the heat is transferred to a working fluid through
a heat exchancer. The working fluid must be cooled and condensed. This
can be accomplished by using cooling water or air. The latter approach—
using forced-draft, air-cooled condensers—has been specified for the hot
dry rock source(w~2^) in order to avoid thermal pollution of water
bodies and to have freedom in siting. The authors state that "the
economics for this type of geothernial power arc- so favorable. . .that
the additional...generating costs associated with the air-cooling equip-
ment can easily be absorbed".
Wastcwater. The experience at the Geysers seems to indicate that waste-
water is not a problcu for dry steam sources. This results from the
fact that the underground fractional distillation of steam leaves the
majority of the dissolved minerals behind.
However, the surplus water remaining after evaporation in the cooling
towers contains trace chemicals which preclude its discharge into the
local streams. The water would require further treatment, or as at
the Geysers, must be reinjected into the ground in deep wells. This
amounts to about 20 percent of the condensate. For 100 MW of generating
capacity, this amounts to over 1 million galIons/day. One large injec-
tion well can accommodate this flow. Thus, a 1,000 MW plant might re-
quire several large injection wells.
A more difficult problem arises when the geothermal wells produce hot
water, or a steaii/water mixture. In these cases the surplus water
muct be disposed. In GOF.C instances, when these wastes arc high in
mineral content, they cannot be discharged into surface waters. Unless
very well mixed, even ocean discharge could lead to severe local effects
if the plant waste differed substantially from ocean water.
At Cerro Prieto, in Mexico, the waters contain about 2 percent salt
(ocean water contains 3.3 percent salts) . For a geothemal electric
plant located here and of 1,000 1-M size, it has been calculated that
saltwater would be produced at a rate of approximately 150 million
gallons/day, or over 150,000 acre-foot annually. For a 2 percent
brine solution, 12,000 tons/day of salts would result if the water was
evaporated away. For the 20 percent brine found in the Salton Sea
area, 120,000 tons/day of salt would result. This poses a monumental
solid disposal problem, and constitutes a real environmental danger>w~-7'
Thus, the disposal of brines is a serious environmental problem.
The method that appears most promising is disposal into injection wells.
An injection well is drilled to a depth where a porous formation will
accept the water. To avoid contamination of ground waters, these
depths may involve several thousand feet. After overcoming original
well-head pressure, it is often found that the water can be literally
poured down the hole. This method has found wide use for disposal of
oil well brines and industrial wastes. One must take care to avoid
aquifers that connect to areas where the waste will do harm, e.g.,
547
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sources of agricultural or potable water. This is not thought to be a
problem in geothermal areas. Should this proposed technique prove
successful a major environmental problem facing geothermal power will
have been eliminated.
Air Pollution Factors.
Air Pollution. Noxious gases are often a by-product of geothermal wells
and hydrogen sulfide O^S) is generally the most prevalent. It exists
in the steam with other gases, most notably carbon dioxide. The r.oncon-
densable gases average 1 percent of the steam flow at the Geysers. (W~30)
Of this, 79 percent is C02, 5 percent methane, 1 percent hydrogen, 3
percent inerts, 5 percent H£S, and 7 percent ammonia.
The above figures indicate that l^S is present in the steam to the amount
of 500 parts per million (ppm) . If a total of 1,000 MW of power were
produced there, this would require 430 million pounds/day of steam. Thus,
215,000 pounds/day of l^S will be released. Other figures (w~31) suggest
that the amount of I^S released at the Geysers would be less, about
100,000 pounds/day.
Using the data from Cerro Prieto, an estimate can be obtained of the
amount of ^S that might be found in a field yielding hot water. It has
been reported(w~32) that H2S is present in the amount of 0.26 percent by
weight in the steam. Other data supplied by the geotherraal project at
the University of California at Ri \erside indicate substantially smaller
amounts, with wide variations between individual wells. If the higher
value is assumed, and a steam rate (20 pounds /kvhr) , a 1,000 MW plant
would Dead to the production of 1,230,000 pounds/day of l^S. This number
exceeds that found in fossil plants burning hi&h sulfur fuel. Thus, it
is seen that noxious gas control is apt to be an essential part of geo-
thermal power production. If necessary, technology is available to pre-
vent the release of these gases if extensive fields are developed.
In addition to l^S , there most certainly could be other chemical species
which would adversely affect the environment if discharged. into the
atmosphere. Some of these might be Radon-222, lead 210, or ammonia.
Other emissions associated with drift from the cooling 'towers , e.g.,
boron, heavy meLals, and fluorides, can degrade the surrounding environ-
ment. Rain water and other natural processes may spread this over a
larger area. The severity of any of these contaminations will be site
dependent and must be weighed separately and carefully. In general,
solutions can be found to prevent this contamination; the most drastic
would be an enclosed system.
Thermal. The significant environmental effect to be expected in routine
operation of a geothermnl. power plant is heat rejection. All power
production cycles using thermal energy reject heat, and the less effici-
ent they are, the greater is the heat rejection. Geothermal steam is
available at low pressure and temperature, when compared with that from
conventional boiler or nuclear plants. Thus, the heat rejection will
548
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be higher. This is clearly indicated by the comparative steam rates
(which can be roughly equated to comparative h6aL rejection) for the
Geysers and a modern fossil plont. The rate for Geysers' numbers 3
and 4 plants is given as 18.53 pounds/kwhr, while Moss Landing 6 and 7
is shown as 6.68.
For 100 psi inlet conditions, and a water tower-cooled condenser, ther-
modynamic calculations show that. 3,630 KW of heat are rejected by a
1,000 MJ geothermal electric plant (a 1,000 Ki-J nuclear power plant re-
jects approximately 2,000 MH of heat). Water yielding geothermal fields
can be expected to have heat rejection rates several times this.
If air-cooled condensers are used, the rejected heat will be Jarger
and will go directly to heating the atmosphere. How this heated air
would distribute itr.elf and affect the local climate will require de-
tailed consideration of local conditions. If water cooling towers are
used, the temperature would be affected to a lesser extent, but sub-
stantial quantities of water would be evaporated, thus influencing the
humidity. Considering the heat rejection rate, and for typical cooling
tower performance, up to 50,000 acre-ft/yr of water will be evaporated
by a 1,000 MM plant.
This amount of reject energy is small when compared to the solar heat
input over even ]0's of square miles. Thus, no large-scale environ-
mental effects are expected. However, in the immediate vicinity of a
concentration of several 1,000 MVJ plants, considerable environmental
effects are possible.
Well Blow Out. In any well driving operation involving high pressure
fluids, the possibility of a wcJl blow out must be considered. Such a
blow out affects land, water, and air. For this reason, it is con-
sidered separately.
The classic oil well blow out is one type that can occur. Such a blow
out can release large quantities of brine if it occurred in a water
yielding geothermal field. The release of the brine into waterways
and agriculture areas would cause severe local environmental problems.
Listed in Table W-5 are the typical environmental burdens that might be
experienced with a. 1000 MW geothermal plant.
Energy Systems Development Cost
As indicated, geothermal energy is commercially utilized today on a
small scale. However, a program to expand its utilization on a major
scale has been described on a preliminary basis in September, 1972, by
W. Hickel, et al.(w~23) This program includes the following subject
areas:
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TABLE W-5. BURDEN-OF ENVIRONMENT 1,000 MW GEOTIIER.MAL PLANT
(Subject to very wide variation with source of
gcotliermal heat and recovery system used.)
Effluent or
Environmental Effect
Quantity
Anticipated
Regulation
Thermal Effects
Air Pollution
Contaminants
Wctcr Pollution
Contaminants
Land Despoilment
Geological Effects
Seismic and
Subsidence
dry steam 4,000 KW
wet steam 10,000 MW
NO _ - No problem
X
SO. - dry steam
Geysers
wet steam
3(10) tons/year
,5
Cerro Frieto 2(10) tons/year
Solid ParLjculate - No problem
Truce chemScal
species
Variable by
0 to
site, tons/year minimize
dry steam 3(10 ) gal/year 0 release
containing 10* ton/year solids
Geysers
wet steam 5(10 ) gal/year
containing 5(10)5 tons/year -
Ccrro Trieto
5(10) tons/year -
Sallon Sea
3,000 - 5,000 acres
Possible problem of
unknown extent. Cost
of monitoring must be
considered.
(a)
None
allowed
Ecological Effects
Social Effects
Noise
Visual Impact
Minor
Great
Great
Minimize
< 100 db
Minimize
(n) Ccrro Pricto will be operating in January 1973. Environmental infor-
mation available after startup and actual operation will be valuable
'for future assessments.
550
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Resources Exploration
Resource Assessment
Reservoir Development and Production
Utilization Technology and Economics
Environmental Effects
Institutional and Legal Aspects.
The research needs of each of these subject areas was explored in de-
tail for 2 days by a panel of 8 to 10 recognized experts (total about
60). Thus, the results of these efforts represent the latest opinions
of the most knowledgeable people working in the area. Table W-6 tabu-
lates their recommendations for the 1974 to 1983 decade. Other funding
recommendations could be made but it is felt that the immediacy of these
recommendations, plus the combined knowledge of the assembled experts,
is sufficient to justify its use here. However, this particular aspect
should be studied in more detail in the future.
Compilations of the estimate of R&D costs are shown below.
Estimated Costs for Geothernal R&D Program
R&D Cost Range - $500 million to
$1 billion
R&D Time Range - 5 to 15 years
Estimated Funding Effort and Requirements
(millions' of 1972 dollars)
Expenditure Expenditure Through the Year
to date (for each period)
1972 1975 1980 1985 1990 Beyond 1990
$10 $110 $420 $270 $250 $300
The estimates of the amount of energy that can be developed vary widely.
An estimate number for the United States by the year 2000 is 400,000
megawatts.CM"23i W-33)
Effectiveness and Economic Costs for Pollution Control
A very preliminary estimate of the cost to achieve forecast require-
ments for pollution control is shown in Table W-7. The primary en-
vironmental burden is from waste heat. The low thermal efficiency
0\<20 percent) results in rejection of 4,000 MW of heat for 1,000 MW of
capacity. If it is assumed that such a plant uses the same types of
heat rejection systems as current fission power plants and that the two
types of plants have the same MW capacity, the cost for the waste heat
dissipation system for the geothermal plant then becomes dependent pri-
marily on the thermal efficiency of the plant. For the most probable
range of thermal efficiencies, the relative cost of the waste heat
dissipation systems for a 1,000 MW geothermal plant are as follows:
551
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TABLE W-6. PROPOSED GEOTHERMAL RESOURCES RESEARCH PROGRAM
(Xillions of Dollars)
Fiscal Year
1574 1975 1976 1977 1973 1879 193C 1981 1932 1983 Total
Resource Exploration 5.0 8.0 11.0 9.5 6.0 3.5 2.0 1.5 1.5 1.5 49.5
Resource Assessment 15.6 23.4 27.S 29.4 31.2 30.4 30.3 31.3 30.3 24.0 273.7
tn
ro
Reservoir Development
and Production 5.0 13.5 27.0 44.0 48.0 21.5 23.0 13.0 10.5 10.0 215.5
Utilization Technology
end Econonics 9.9
0.9 11.9 11.3 10.5 9.1 9.1 9.1 9.1 9.1 99.5
Environmental Effects 4.2 4.2 3.8 3.6 3.5 3.3 3.3 3.4 3.4 3.3 36.0
Institutional
Considerations 2.0 2.0 1.3 1.3 ^j.Q __0.3_ 0.5 0.5 0.5 0.5 10.S
Totals
41.7 61.0 83.0 • 99.S 100.2 63.3 68.2 58.3 '. 55.3 43.4 684.7
-------
Relative Cost for •,
Thermal Efficiency Waste Heat Dissipation System
10 2.47
15 1.87
20 1.52
25 1.28
33.3 1.00
TABLE W-7. EFFECTIVENESS AND ECONOMIC COSTS (1972 Dollars)
FOR POLLUTION CONTROL WITH RESPECT TO MEETING
EXISTING AND ANTICIPATED REGULATIONS
(Geothermal Power 1,000 MW Plant—Capital Costs Only)
Effectiveness,
percent Cost;, $
Thermal effect
Mr pollution
Water pollution
Land despoilment
Geological effects
Social effects
95.0
99.5
100.0
90.0
90.0
90.0
20,000,000 - 50,000,000
5,000,000
5,000,000
5,000,000
2,000,000
2,000,000
Thermonuclear Fusion
Introduction
It is generally recognized by scientists that controlled fusion will
play a central role in meeting the energy requirements in the near-
term future. This recognition is based on favorable technical factors
and on a consideration of alternative fuel reserves. The technical
outlook was recently reviewed by the Joint Committee on Atomic
Energy(W~34) and progress in theoretical descriptions and confirming
experiments have permitted optimistic projections for scientific feasi-
bility demonstration experiments and subsequent controlled thermonuclear
reactor (CTR) systems. The impetus for fusion which derives from a
consideration of fuel reserves is illustrated in Table W-8. These re-
sults clearly show the relative shortage of fossil and rich-ore ficsile
fuels are the driving force toward CTR.
The basis for fusion power is the energy released in combining light
elements with a. consequent release of nuclear binding energy. At
ordinary temperatures these nuclei are prevented from combining by
electrolystatic repulsion but fusion can be achieved if these nuclei
553
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must be heated to temperatures near 50,000,000 C to provide sufficient
thermal energy for fusion reactions to occur at a useful rate. At
these temperatures the nuclei are completely stripped of electrons and
the subsequent electron/ion region is referred to as a plasma.
TABLE 17-8. WORLD ENERGY RESERVES OF "INFINITE FUELS'1^"35 >W~36 >U~
Years at 2.8x10 Btu Per
Energy Source Known Possible
Fossil
Coal 6.8 100
Oil and Natural Gas 1.8 25
Total 8.6 130
Fissile
Rich-Ore Burners 2.7 , 7.1
Low-Grade Ore Burners 1.0(10) 3(10) '
Rich^Ore Breeders 107 340
Low-Grade Ore Breeder 3.4(10) (10)
Total Rich Ore 110 347'
Total Low-Grade Ore 3.5(10) (10)
Fusion „
Deuterium (10):. (10)
Lithium (10) (10)6
.Solar (10)JU (10)
ao
(a) The value of 2.8x10^8 utu is the quantity estimated to rseet pro-
jected world population needs with per capita consumption rate of
United States in 1970.
There arc a number of energy cycles which can potentially be used in
a CTR. Some of the more prominent cycles are shown in Table W-9. In
addition to these cycles, there are other reactions with isotopes of
higher Z number which can undergo fusion.(W-38) Their application is
not as promising, at this time, however, as the reactions displayed in
Table W-9. In Table W-9, the initial reaction, the deuterium-tritium
(D-T) reaction, is the reaction that probably will receive the bulk of
the attention in the early commercial stages of exploitation of the
fusion process because the ignition temperature is lowest. Therefore,
the rest of this discussion will center around this particular energy
cycle. - In the D-T reaction the available energy resides in an ener-
getic neutron; in other cycles the energy can largely be found in
charged particles. It is worth pointing out that any deuterium fueled
554
-------
fusion plant would have all of the reactions given in Table W-9 taking
place to some degree. Therefore, problems identified with the D-T cycle
would exist to some degree in other fuel cycles.
TABLE W-9. PROMINENT CTR ENERGY CYCLES
Reaction Reaction Products Total Energy (Mcv)
23 41
11 2 o
H2 . ,,2 H3 1
l" + l" 1H + 1H
22 31
jlT + Lr 2HeJ + Qn
17.6
4.03
3.27
18.3
Description of the Energy System
Because significantly high-power levels have yet to be demonstrated in
the laboratory, it is premature to discuss the design of a CTR power
plant. However, based upon the available experimental data and some
informed speculations, one can describe some of the main features of a
conceptual power station.
Two distinct methods are being seriously considered for creation of a
controlled thermonuclear reaction. They can be grouped according to the
scheme proposed for confinement of the ion plasmas. In order to create
a controlled thermonuclear reaction, it is necessary that one create a
hot gaseous plasma of the desired reacting constituents (i.e., deuterium
and tritium) and that this plasma be confined for a time period which is
long compared to the fusion reaction time. The two methods which have
been proposed for confinement are the electromagnetic confinement method
and the inertial confinement method.
The electromagnetic confinement method is based upon the observation that
plasma containing energetic ions can, in principle, be shaped by one or
more electromagnetic fields. This method of confinement has received
the bulk of the research effort to date.^ 39> °' Several geometric
configurations have been proposed for developing the required magnetic
fields. The configurations can be broadly classed as the cylinder or
open geometry and the toroidal or closed geometry. In the open geometry
a magnetic field confines the plasma in a long cylinder and magnetic
"mirrors" are placed at the ends of the cylinder to minimize end losses.
In the closed geometry a continuous torus is used as the confining geo-
metry. Both the mirror and torus geometries are distinguished by a
555
-------
number of different conccpLs which involve varying geometrical condi-
tions, magnetic field configurations, and plasma conditions. At the
moment, the most successful approach appears to be the Tokamak varia-
tion of the torus group. In the Tokamak system large currents induced
in the plasma provide strong resistive hnating and supply an important
component of the confining magnetic field. Since the field is gener-
ated by induced currents instead of external windings, a compact fusion
reactor is possible in a toroidal geometry. Successful experiments in
the USSR in 1968 have turned worldwide research attention to Tokamak.
In most considerations of magnetically confined systems the facility
costs force the system toward large generating capacities, typically
10,000 MWt.
Inertial-confinement systems are based on heating the fuel at a rate
which is fast compared to the expansion of the resultant plasma. One
of the fastest developing inerfial-confinement concepts involves laser-
induced microdetonations. (W-35, W-41) Major improvements in design have
made giant pulsed glass lasers available at an acceptable cost. These
are capable of delivering the necessary energy in short bursts (about
10,000 joules in one billionth of a second or less), and are believed
to be adequate for demonstrating feasibility. The relatively low effi-
ciencies typical of glass lasers are a disadvantage that can probably
be overcome either by further development or, to speculate a little,
by devising suitable gas lasers; efficiencies approaching 50 percent
have been reported for carbon monoxide lasers. One strong advantage of
this concept is that it eliminates the need for large superconducting
magnets which are required for the electromagnetic approach. This per-
mits system designs of smaller total generating capacity,, perhaps a
few-hundred MWt.
Both the magnetically-confined and inertially-confined concepts employ-
ing D-T share the need to produce tritium artificially because natural
supplies are insufficient to support the need. Figure W-3 illustrates
this cycle. Lithium is placed in the blanket to jccomplish this goal.
Therefore, the D-T energy cycle can be thought of as a deuterium-lithium
(D-Li) cycle, and, in fact, the viability of this cycle is limited by
the available lithium supply although the known lithium reserves have
been estimated to be adequate for tens of thousands to millions of
years.(W-35, W-37)
The fuel cycle shown in Figure W-3 would, of course, vary somewhat de-
pending upon the final CTR design. However, the major processes have
been identified. Recovery of deuterium (from fresh or seawater) is a
complex but well understood technology by itself. Presumably, the
mining and refining of lithium metal can be readily defined. The re-
covery, handling, and injection of tritium bred in the reactor blanket
is somewhat less well understood, but it is accepted that these functions
are necessary.(W-42)
A number of different energy conversion schemes could be utilized depend-
ing upon the specific characteristics of the plasma and design of the
556
-------
Deuterium
Supply
(From
Water)
Lithium
Mining
Fuel
Manufacture
and Injection
_/• v
Tritium
Processing
Electrical
Energy
CTR
Power
Station
T
Ash
Tritium
Recovery
FIGURE W-3. CONCEPTUAL DEUTERIUM TRITIUM FUEL CYCLE
557
-------
reactor. IL would seem likely that the initial power plants would cm-
ploy conventional steam turbines. A second generation plant could pos-
sibly employ a liquid metal Lopping turbine, as suggested by some in-
vestigators, (W-43) to improve plant thermal efficiencies. If developed,
large-scale gas turbines would be particularly attractive for applica-
tion to CTR power plants. Finally, because a significant fraction of
the energy of some fusion reactions is given off in the form of charged
particles, a direct conversion scheme similar to the operation of a
charged particle accelerator in reverse, appears conceptually possible. '
In this case presumably the unit would have both a direct and an indirect
conversion system with resultant high net thermal efficiency.
Both the magnetically- and inertiall>-confined systems woul'd employ some
form of a pressure vessel to contain the plasma vacuum. Certain exotic
metals capable of high-temperature duty, such as vanadium, molybdenum.
and niobium have been suggested for the structural component of this
vessel. At the present time, there is not sufficient data to make a
clear selection and, in any case, it would appear that the initial plant
would employ steel as the vessel structural material. The more exotic
metals would probably come into play with the development of a second
generation unit.
Based upon the previous discussion, one can develop a rough conceptual
design of a power station based upon the two confinement methods. The
major elements of such a station arc:
o A plasma confinement and heating scheme
e A plasma vacuum vessel
o A moderating and shielding blanket
e A fuel handling and refueling system
o A power conversion unit.
Based upon these elements, Figures W-4 and W-5 display conceptual de-
signs of probable first generation CTR power stations. Figure W-4 shows
an electromagnetic confinement station and Figure W-5 shows an inertial
confinement station.
Detailed cost estimates for cither magnetically-confined or inertially-
confined systems cannot be made because plant engineering cannot pro-
ceed without basic design information. In general, however, among the
crude estimates that have been made, the reactor plant equipment and
nuclear engineering costs for the magnetically-confined systems are
slightly higher than those for breeder reactor systems and these costs .
for the inertially-confined systems are competitive with these systems.
An example of projected costs for a magnetically-confined system
Nuclear Boiler $60-70/kw(e)
' Magnets $30-60/kw(e)
Fuel 0.00035c/kwhr
Other $70-100/kw(c)
«/$200/kw(c)
558
-------
Laser
Beam
Heater
in
Pellet
Injection
Shield
Blanket
Vacuum
Vessel
Plasma
Fuel
Recovery
Steam
^Generator
Electrical
Generator
Steam
Turbine
Condenser
Pellet
Manufacture
Fresh Fuel
FIGURE W-4. CONCEPTUAL DESIGN OF AN INERTIAL CONFINEMENT CTR POWER PLANT
-------
in
s
Steam
/Generator
Electrical
Generator
FIGURE W-5. CONCEPTUAL DESIGN OF AN ELECTRO-MAGNETIC CTR POWER PLANT
-------
Environmental Burden
One principle advantage of a fusion power system over a fossil system
is the total absence of combustion products; this advantage is shared
with fission plants. Another advantage of fusion power is that radio-
active vaste is localized relative to fission plants because no fission
product inventory, or radioactive material reprocessing, is associated
with the operation. The possibility of direct conversion of the highly
charged fusion products into electricity with the attendant advantage of
thermal efficiency has been cited.(W-46) Another noteworthy advantage
of fusion power is the freedom from a nuclear excursion or criticality
accident which is a concern of all fission power systems. This is a
consequence of the physics of operation; fusion entails no "critical"
quantity of fuel and the associated possibility of an "over criticality"
condition.
Although these relative advantages exist, fusion power will have an en-
vironmental impact. Except for the direct conversion concepts, a
conventional thermodynamic cycle is contemplated with the accompanying
problems of thermal effluents. Probably higher temperatures will be em-
ployed with the attendant reduction in waste heat per unit electrical
power, but this is usually a modest savings (perhaps 15 to 20 percent
at best). The fusion plant will likewise have a chemical discharge from
coolant treatment and other metal/chemical discharges. These are not
unique to the system and, therefore, are not discussed further here.
The effluents which are peculiar to a fusion reactor power plant are
summarized in Table W-10.
TABLE W-10. SUMJIARY OF EFFLUENTS FROM D-Li ENERGY CYCLE
Effluent
Source
Release Point
Tritium
Fusion Ash
(2He*, etc.)
Waste H20
Lithium Tailing
Radioactive Waste
Bred in Reactor from
Lithium
Created in Reactor
Deuterium Collection
Mining Process
Neutron Reactions with
Structural Components
or Reactor
Leakage Through Reactor
Wall
Release from Plant
Isotope Separations Plant
(Back to Source)
Refining Process
At Plant Disassembly or
561
-------
Of the effluents created by tlie D-Li energy cycle, tritium lias probably
the largest potential environmental impact. • The D-Li energy cycle would
consume .2 kg of tritium per day per 1000 MWt. The station inventory
has been estimated to be between 1 to 15 kg per day per 1000 MWt;(w'*7)
this is about 1,000 to 100,000 rimes the lithium inventory in a fusion
plant. If the inventory per 1000 Ml.'t is 1 kg, the plant leak rate must
be .0012 percent per day in order to meet existing regulatory standards.
The current technology for leak rates on large systems such as nuclear
power stations is higher by one to two orders of magnitude.(W-39)
As currently envisioned the radioactive waste associated with the D-Li
energy cycle comes primarily from neutron-induced structural activation.
If stainless steel is used the activation rate is expected to be com-
parable to vanadium or molybdenum whose long-term activity has been
estimated to be one-thousandth that of a comparable fission power
plant.(W-47) if niobium is selected ns the base structural material,
radioisotopes of Nb, Y, and Zr will be formed and activity comparable
to a LMFBR can be anticipated. While the opportunities for dispersion
of this material do not exist in a manner comparable fo an LMFBR, it
does represent an ultimate burdan on the environment. A more detailed
evaluation of this is needed.
Small quantities of the ash from the fusion process would be released
from the D-Li fusion cycle. The D-Li cycle will produce and presumably
release about 250 grams of 2!le l Per day Pcr 1000 l-Vrll.
In order to separate the deuterium required for the D-Li cycle, it will
be necessary to use, in a nonconsur.ipLive manner, some 16,000 gpn of
seawater per 1000 MWt of installed capacity to meet the makeup fuel
requirements of the plant.(W-48) By comparison, about 240,000 gpm of
cooling water would be required to disperse this amount of heat.
The lithium mining cycle would produce measurable quantities of efflu-
ents. Perhaps the best way to characterize the mining problem is by
way of comparison to the uranium fuel cycle. Assuming a strategy based
upon total use of both fuels, about one-third as much lithium needs to
be mined as compared to uranium (by weight) provide the same power level.
In terms of inventory, however, the lithium requirement would be several
times that of the uranium. Thus, the lithium mining impact can be ex-
pected to compare to the uranium mining impact.
The potential impact of effluents is summarized in Table W-ll for a
1000 MWc power station employing an operating efficiency of 40 percent.
Many of the results in Table W-ll are speculative and must remain so in
the absence of a designed and operating station.
Development Schedule and Costs for Fusion Power
An estimate of 4.24 billion dollars to bring fusion power to the point
of commercial viability has been made by the R&D Goals Task Force of
the Electric Research Council.(W-49) xi,is figure is broken down by
milestone (or function) in Table W-12 and by year in Table W-13. Also
562
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included in Table W-L3 are the Atomic Energy Commission'estimates for
on expanded program and an all-out program are compared with the Electric
Research Council figures through the year 1980.
TABLE W-ll. D-Li ENERGY CYCLE EFFLUENTS 1000 MUe, 40 PERCENT
EFFICIENCY
Effluent . Amount Released Assumptions
Relative
Impact
Compared
' to LWR
Tritium
Heated Effluent
Fusion Ash
Waste Water
Lithium Tailings
Radioactive Waste
.41 Rem/day
5.9xl09 Btu/hr
.63 kg/day
40,000 gpm
35% of uranium
1-5% of LWR
.0005% leak rate; 5
kg inventory
40% thermal efficiency
Total release
Makeup only
Ultimate use
Stainless structure
Comparable
Comparable
Trivial
Trivial
Comparable
Small
TABLE W-12. NUCLEAR FUSION COSTS (BY MILESTONE)
Expended Through FY 1971
Proposed
Demonstration of Feasibility
Physics, Engineering, and Materials
Direct Conversion Prototype
Thermal Prototypes (2)
Demonstration Plants^3'
Total, future
Millions of
1971 Dollars
400
(a) Incremental cost for small plants above equivalent fission capacity
in large plants. If very large (2,000 to 5,000 MW) demonstration
plants are necessary, this figure is too low.
Effectiveness and Economics of Pollution Control
i
At present there are no low cost systems for isolating and storing tri-
tium leaking from a reactor system. The tritium usually appears at a
very low concentration in air or water streams such that concentration
by known methods would be very costly. It is assumed herein that no
attempt is made to isolate tritium escaping from the system.
563
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TABLE W-13. NUCLEAR FUSION COSTS BY YEAR ''IN
MILLIONS OF 1971 DOLLARS
AEC Estimates
Year Utility Estimates Expanded Program All-Out Program
1973
1974
1975
1976
1977
1978
1979
1980
1981-1985
1986-1990
1991-1995
1996-2000
60
95
110
135
160
170
215
245
1000
1000
500
500
45
58
65
76
81
83
86
89
—
—
--
--
74
143
190
215
237
.-
__
--
• _
--
--
--
Escape of 2^e creates no environmental problems. It is assumed that
no waste treatment systems are necessary.
No treatment processes are assumed necessary for the wastewater from
deuterium production processes. Normally that water is of equal or
better purity than when it was obtained from its source. In some cases,
though, treatment may be necessary for removal of residual corrosion
inhibitors or process chemicals.
The waste heat from a fusion device must be dissipated either in a
water or air sink in the same manner as for current power plants. The
costs for constructing and operating the waste heat system may be lower
per MHc of capacity than for LWR because the fusion reactor could possi-
bly have a higher thermal efficiency and a higher power level.
There have been no attempts to extract in detail from the overall R&D
costs those associated with environmental quality control. Some paral-
lels might be drawn with fission power sources. In that area it is
recommended that -15 million per year be spent on environmental control
research. This is a few percent of the total budget for research.
There is much in common between fusion and fission so it might be ex-
pected that the additional needs would be lower—say 1 p'ercent of the
total R&D costs. This would mean that an additional 40 million dollars
would be required to meet environmental research needs over the next 20
to 30 years if the total estimated cost of Table W-12 is accepted. Apart
from these estimated research costs a continuing radioactive materials
management cost has been estimated to be 0.03 to 0.05 mill/kwhr.(w-5°)
564
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Breeder Reactors
Fission Gas-Cooled Fast Breeder Reactor
The gas-cooled fast breeder reactor,(w~5^» W-55, W-56, W-57) as pre_
sently visualized, will utilize metal-clad refractory fuel in a core
that is cooled by the forced circulation of pressurized gas. The con-
cept involves a wedding of Ll-lFBR fuels technology and gas-cooled thermal-
reactor (AGF and HTGR) component technology. The development of the
GCFBR lags behind that of the LMFBR by five to ten years with only a
relatively low level of current effort. It is doubtful that it will be
a commercially significant source of power until tlie'end of this cen-
tury. The development of large, high-temperature gas turbines would
increase the attractiveness of gas-cooled reactors generally and speed
the development of the GCFBR.
Description of Energy System. Figure W-6 shows a suggested power cycle
for the early 1000 MWe GCFBR1s. A conventional steam cycle is projected
in line with current gas-cooled power plant technology. Core-coolant
exit temperatures are limited by fuel-pin performance limitations which
are in turn directly influenced by the use of stainless steel cladding
on the fuel. The helium is pumped through the core at high flow rates
by means of helium circulators. The heated helium is used to produce
steam in a steam generator and is then recycled to the core. The steam
side of the system contains a conventional turbine for the generation
of electricity.
Potential Environmental Factors. The GCFBR can and will be designed
such that the reactor effluent is well within permissible release limits
to the atmosphere. Because of its relatively high efficiency (^38 per-
cent), thermal effluent will be significantly reduced as compared with
water reactors whose efficiency is only about 30 percent.
The use of helium coolant will result in production of tritium as a re-
sult of neutron reaction with 3He. However, this can be readily removed
by continuous scrubbing of the coolant gas to remove both tritium and
fission-product gases. Disposition of the tritium can be readily accom-
plished because of the small volumes involved. This is not true in
LWR's where the tritium is chemically indistinguishable from hydrogen
and one is confronted with the processing and storage of relatively
large amounts of tritium-contaminated water.
Fission-product contamination of the reactor system will be minimized
in the GCFBR by venting of the fuel to a collection system. Thus, only
minimal release to the coolant will occur in the event of a fuel failure,
Since helium is inert, leaching of fission products from the fuel by the
coolant will not occur as in water and liquid-metal systems. Release
in any event will bo restricted to volatiles. Since only a gas phase
will appear in the complete primary circuit, only a single recovery
system will be required.
565
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Tidal Power
Because of the 24-hour, 50-minute Liclal cycle, the availability of en-
ergy from tidal flow in large estuaries gradually shifts throughout the
day. Thus, when large slugs of energy become available .from tidal move-
ment at times of low demand on the system, pumped storage is required
to utilize the tidal output effectively. Hence, recent consideration
of tidal power has included pumping plants as well. (^~->l-) A pumped-
storage facility involves additional capital investment, already a seri-
ous limitation of proposed tidal power plants.
Only one major tidal power plant is in operation today—at the Ranco
River estuary on the coast of France near St. Halo. Rated at 240 MW,
with a 3,000-foot dan impounding 6.4 x 10" cubic feet of water using
two-way bulb turbines, the plant generates 6.24 x 10^ kwhr annually for
an availability of about 30 percent. Power generation costs are high
compared with modern steam plants, amounting to 2 to 3 times the bus-
bar costs of fuel-fired systems because of the high capital charges in-
volved in building a large dam, providing pumped-storage basins to supply
power between tides, and in constructing the turbine pumps.
Environmental Burden
Tidal power has little impact on the environment, mostly involving local
actions resulting from disturbing normal tidal flow patterns. Changes
in salinity, oxygen content, and water level may affect local fisheries,
but no major effect is foreseen on climate or on atmospheric conditions
in general.
R&D Requirements
Little R&D is required, the operation at Ranco River having provided a
"pilot plant" demonstrating both the cost and the feasibility of tidal
power plants. The Pr.sscnunquoddy situation lias been reviewed many .times,
the conclusions being that the cost of the required dam and the pene-
trating facilities cannot be justified. Dam-co'i-struction techniques are
not likely to change unless, some day, nuclear explosives might be util-
ized in some predictable manner. Likewise, bulb turbines as used at
Ranee River and in pumped-storage installations perform satisfactorily.
Because of the inherent low hydrostatic heads, some turbine development
may be desirable, 0''~52) but no appreciable power generating gains can
be expected through further research.
All of North America is estimated to have some 300,000 MW of tidal en-
ergy. (w~53) T|ie potential for power generation is therefore weak, and
coupled with the high capital cost, tidal power is not considered a
viable source.
For the above reasons, no funding effort appears to be needed.
566
-------
575 .
'Net Plant Output 1000 MWe
Plant Efficiency 38%
(All data are estimated for
purpose of this report only)
FIGURE W-6. SIMPLIFIED POWER-CYCLE DIAGRAM, 1000 MWe GCFBR
Because o'f the higher pressure on the helium side of the steam genera-
tor, there is a potential for leakage to and contamination of the steam
system. While this can be minimized by appropriate maintenance of the
steam generator and cleanup of the helium gas, waste treatment systems
will be required to clean up the steam circuit also in order to prevent
the -possibility of leakage to the atmosphere. However, the potential
would appear to be less than from any LWR.
Fission products not recovered on site will eventually be recovered
during reprocessing. Most fission products and tritium will require
long-term storage to avoid radioactive contamination of the atmosphere.
Fast reactors ara fueled with plutonium which is highly toxic if in-
haled or ingested. Shipment of the virgin fuel will require precautions
similar to that required for its shipment after irradiation.
The great advantage of fast breeder reactors, of course, is in their
negative fuel usage. The GCFBR is anticipated to exhibit a breeding
ratio of at least 1.5, meaning that for each unit of fuel consumed, 1.5
times as much is generated for a 50-percent gain. The fuel is 239pu
and smaller amounts of 241pu an(j tne fertile material from which addi-
tional fuel is bred is ^38ut The goal in fuel performance is to achieve
an electrical power output of at least 10° kwhr/kg of fuel and fertile
material before it must be reprocessed.
Energy Systems Development Costs. A wide range of development efforts
arc required to bring the GCFBR to the stage of commercial feasibility.
However, the most critical involve (1) core-cooling requirements in the
event of less of helium pumping power; (2) improved fuel-pin design, in-
cluding consideration of cladding material, fuel venting, and surface
heat transfer; and (3) design of the necessary pressure vessel.
567
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An estimate of required R&D costs and time prior to construction of a
commercial size GCFIJR LOGO f-F.Vo power plant and including construction
of a smaller ( 300 MWe) demonstration plant is given below.
R&D Cost Range $750,000,000
R&D Time Range 20 years.
Fission-Molten Salt Breeder Reactor
The Molten-Salt Breeder Renctor(w"58» W-59) (usr.R) is a thermal reactor
concept operating on the 232jj1_233u £uc^ CyCic uhich is capable of breed-
ing by continuous removal of fission product wastes and 233pa from the
fuel-containing salt. The Pa decays to 233[j which is then returned as
fuel Lo the reactor. Research and development already accomplished on
MSER materials and processes indicate that after the technology has been
extended in a few specific areas, a prototype MSBR could be successfully
constructed and operated.
Molten salts have been under study and development as reactor fuels and
as coolants for over 20 years. Their chemical, physics, and irradia-
tion properties are excellent. The Molten-Salt Reactor Experiment (MSRE)
contributed significantly Lo MSR technology during its 5 years of opera-
tion. 'Research in the processing of molten salt fuels showed that^33pa
and fission products could be separated from salts containing both uran-
ium and thorium by reductive extraction into liquid bismuth. Oak Ridge
National Laboratory (ORNL) has prepared a conceptual design for a 1000
MWe single-fluid molten-salt reactor power plant that indicates such a
plant is technically feasible and economically attractive.
The major remaining areas for development in the MSBR concept are:
1. The chemistry of noble metal fission product behavior
2. Alternate rare earth removal processes
3. Physical and chemical properties of the secondary coolant salt
4. Continuous methods for analytical process control
5. Engineering development of fuel processing equipment for contactor,
fluorinator, electrolyzer, and vacuum distillation
6. Improvement in materials such as radiation-damage resistant graphite,
container materials (Hastelloy N), and container material for simultane-
ous contact of molten Bi and salt at 500 to 700 C
7. Reactor system components such as pumps, heat exchangers, steam
generator, rods and drives, and maintenance procedures.
Description of the Energy Svstpm. The reference MSBR operates on the
_u cycle, with botli fissile and fertile materials incorporated i.n
568
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a single molten-salt mixture of the fluorides of lithium', beryllium,
thorium, and uranium. This salt, with the composition LiF-BeP2~ThF4-
UF4 (71.7-16.0-12.0-0.3 mole percent), has a liquidus temperature of
930 F (772 K), has good flow and heat transfer properties, and has a
very low vapor pressure in the operating temperature range. It is also
nonwetting and virtually noncorrosive to graphite and the Hastelloy N
container material.
The 22-foot diameter by 20-foot high reactor vessel contains graphite for
neutron moderation and reflection, with the moderating region divided in-
to zones of different fucl-to-graphito ratios. As the salt flows upward
through the passages in and between the bare graphite bars, fission
energy heaLs it from about 1050 F (839 K) to 1300 F (978 K). Graphite
control rods at the center of the core are moved to displace salt and
thus regulate the nuclear power nnd average temperature, but these rods
do not need to be fast scramming for safety purposes. Long-term reac-
tivity control is by adjustment of the fuel concentration.
The core neutron power density was chosen to give a moderator life of
about four years, based on the irradiation tolerance of currently avail-
able grades of graphite. The specific inventory of the plant, including
the processing system, is 1.47 kg of fissile' material per MWe, the
breeding ratio is 1.06 and the annual fissile yield is 3.3 percent.
The heat-power system has a net thermal efficiency of over 44 percent
which makes a reactor plant of about 2250 MWt ample for a gross electri-
cal output of 1000 lF.
-------
FLOW DIVIDER
^ 'F 360QP
101 10° Ib/hr
JL1U
(G«CSS)
I ' 1
CHEMICAL I
I PROCESSING I
I— 1
FIGURE W-7. SIMPLIFIED FLOW DIAGRAM OF MSBR SYSTEM, (1) Reactor,
(2) Primary heat exchanger, (3).Fuel-salt pump, (4) Coolant-salt pump,
(5) Steam generator, (6) Steam reheater, (7) Reheat steam preheater
(8) Steam turbine-generator, (9) Steam condenser, (10) Feedwater booster
pump, (11),Fuel-salt drain tank, (12) Bubble generator, (13) Gas separator
(14) Entrainment separator, (15) Holdup tank, (16) 47-hr Xe holdup charcoal
bed, (17) Long-delay charcoal bad, (18) Gas cleanup and compressor system
The estimated plant capital costs for a fully developed MSBR, although
differing in breakdown, are about the same as those for a light water
nuclear power station. Fuel-cycle costs are expected to be quite low
and relatively insensitive to the prices of fissile and fertile materi-
als. ...
Potential Environmental Factors. The nature of the MSBR system lends
itself -to the minimizing of the environmental impact of a nuclear power
system. Its high efficiency, for instance, reduces the waste heat that
needs to be dissipated to about 75 percent of the waste heat for a light
water reactor.
In normal operation, the fission gases and tritium are continuously re-
moved from the primary circuit in a form that lends itself readily to
collection and packaging. Thus, even though there may be 20 to 50 times
as much tritium produced as in an equivalent LWR, it is less likely to
be released.as water or water vapor to the environment. The nonvolatile
fission products are also continuously separated in a relatively small
volume and form that is readily packaged and stored. Should salts leak
570
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from the system, the tendency will be for them to solidify retaining
the fission products, rat lie r than to evaporate, and disperse the fission
products into the air as a p. LWR. Because of the continuous processing,
the buildup of long-lived fission products is maintained at a minimum.
Thus, a major source of heat in event of an accident is considerably
reduced. By the same token, the fuel inventory is maintained at the
minimum necessary to attain criticality, reducing the potential for an
uncontrolled criticality accident. The primary system operates at low
pressure, and the salt content, is quite inert chemically. Thus, the
primary system contains only sensible heat, as contrasted with the
latent heat of the pressurized water system, and there is no potential
for the metal-water reaction which one finds in the LWR.
i' «
All the above* factors make the MSBR system one whose environmental im-
pact is likely to be considerably less than that of the LWR.
Development Schedule and Cost. An estimate of the required cost and
time for the MSBR system development to be carried through the building
and operation of a demonstration plant (300 MWe) is given below:
R&D Cost Range * $1,000,000,000
R&D Time Range - years from 1972 20 years
Estimated funding effort and requirements to produce a demonstration
plant are:
(Millions of Dollars)
Expenditure Through the Year
Expenditure to (for each period) -
Date. 1972 1975 1980 1985 1990 Key'ond 1990
^$50 $50 $150 $200 $100 ?
The magnitude of energy that can be developed by the year 1990 is esti-
mated at approximately 5 GWe.
Liquid-Metal Fast Breeder Reactor
The Liquid-Metal Fast Breeder Reactor (LMFBR)(w~60• w~6l» W-62> will use
liquid sodium as the coolant and plutonium ('39pu an
-------
loop between the reactor coolant system and the steam, supply system.
Sodium serves as both the primary coolant and the heat transfer medium
in the intermediate loop. Sodium is attractive for both purposes be-
cause of its excellent heat transfer characteristics. An additional
attractive feature of sodium is its high boiling point (892 C at 1 atm),
so that pressurization of the primary coolant system to suppress boiling
is not required.
Reactor
r
f'uel-
• Sleam
FIGURE W-8.
Steam gcneotot
NUCLEAR STEAM-SUPPLY COMPONENTS IN
A LIQUID-METAL-COOLED BREEDER
REACTOR
Potential Environmental Factors. The LMFBR is anticipated to be oper-
able with a 40-percent efficiency. The increased efficiency relative
to a LWR means a decrease by one-third in thermal effluent for an LMFBR
plant of equivalent power. ..
Tritium production in an LMFBR is negligible being restricted to produc-
tion in the fuel by ternary fission and from possible contaminant ^Li in
the sodium coolant by reaction with neutrons. There is no reaction v;ith
sodium to produce tritium.
The LMFBR is potentially capable of zero radioactive effluent release
at the reactor plant site. The primary system will operate at a pres-
sure close to atmospheric with the secondary sodium system at a slightly
higher pressure, both sodium circuits being at a very much lower pressure
than the steam-water system. Thus, the possibility of contamination of
the latter system as a result of leakage from the primary circuit will
be minimal. Consideration is being given to the use of vented fuel pins
that would release fission gases directly to the coolant and thence to
the cover gas system. The recovery for disposition of the fission pro-
ducts from the cover gas and sodium coolant will be required and this
capability is available.
Fission products retained within the fuel will be recovered during re-
processing of the fuel. The fission product volume will be relatively
572
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small but will require long-term storage in a controlled area to per-
mit radioactive decay. The storage area will be determined by the ex-
clusion area required rather than the volume of the waste itself.
Because the plutonium fuel is highly toxic, the shipment of fuel to
the reactor plant will require the same safety precautions as are
needed for shipment of the irradiated fuel. Escape of fuel to the
atmosphere during shipment must be avoided.
The breeder, since it creates fuel, has a favorable impact on energy
resources. The LMFBR, depending upon the specific fuel type and
breeder design, will exhibit a breeding ratio of between 1.2 and 1.5,
the lower value probably being typical of early breeders. The ratio
means that for each unit of fuel consumed, 20 to 50 percent more fuel
is generated than is burned. The use of breeder reactors increases
the energy supply from natural uranium by two orders of magnitude.
The electrical energy production in breeder reactors will amount to
10^ kwhr/kg of combined fuel and fertile material before the fuel is
reprocessed. The gross electrical potential per kg of fuel and fertile
material is about 9 x 106 kwhr.
The breeder also has a favorable effect on energy use. Because plu-
tonium serves as the fuel and can be chemically recovered, the use of
gaseous diffusion plants which consume large amounts of energy is not
required, as in the case of uranium as fuel, which requires isotope
separation.
Development Schedule and Cost. The LMFBR has been the subject of de-
velopment since the mid-lS-'iO1 s, although the level of effort has fluc-
tuated considerably. Several experimental reactors, the EBR-I and
EBR-II, and a prototype power plant, the Enrico Fermi plant (220 MWt)
have been constructed and operated. Nevertheless, the LMFBR is still
unproven commercially and the next step will be construction of a 300
MWe commercial power plant with development of the large size components
required for a commercial plant involving a major effort.
The demonstration plant is projected for operation by 1982. The 1000
MWe plant will probably not be operational much before 1990. Thus, the
LMFBR will not be commercially significant in the United States until
the end of this century.
An estimate of the required cost and time for the LMFBR to reach the
point of commercial utilization, which covers principally the period
up to operation of a demonstration plant, is given as:
R&D Cost Range $1,000,000,000
R&D Time Range 15 years.
573
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MaEnctohydrodynamics
Magnetohydrodynamics (MHD) is an energy conversion process using the
advanced technology of plasma flow that has potential application to
conventional systems for generating power. When an electrically
conducting gas (plasma) is forced through a duct at high velocity in
the presence of a transverse magnetic field, the electromotive forces
decelerating the gas flow induce an electrical current flow that can
be delivered to external load through electrodes appropriately placed
along the duct.
Adequate electrical conductivity in the plasma for practical power
generation requires both high gas temperature (around 4000 F or 2500 K)
and gas flow seeding with readily ionizable materials such as potassium
or cesium. In a combustion gas system, an advanced combustion process
is required to deliver the hot compressed gas with the added seed to
the HUD nozzle where it is expanded into the MHD duct past the magnetic
field and the electrodes. The work extraction lowers the plasma tem-
perature to the regime of inadequate electrical conductivity at about
3100 F (2000 K) so cither a very large regenerative heat exchange with
the combustion air or delivery of thermal energy to another power ex-
traction cycle, or both, is indicated. Some regenerative heating is
necessary to achieve the ultrahigh combustion temperature without oxy-
gen enrichment but practical base lond systems would feed the MHD ex-
haust into a conventional steam plant which generates the majority of
the electrical power.
Thermodynamically, this high-temperature extraction of work from the
combustion products improves efficiency, reducing both the fuel require-
ments for each kwhr of electrical energy (stretching our natural re-
sources) and the heat rejection for each kwhr of electrical energy
(reducing the thermal pollution loading). The cost of seed material
is such that the stack gases must be treated to recover it, inherently
imposing sophisticated gas cleaning elements in the system so that the
pollution demands are more readily accepted. The high flame tempera-
ture, however, imposes a uniquely severe NOX control burden.
Closed cycle MHD systems using either noble gases or two-phase fluids
also have been investigated. The Rankine cycle fluid systems have shown
themselves to be limited to specialized aerospace application. Brayton
cycle MHD systems have been proposed, in particular for gas-cooled re-
actor systems, but basic incompatibilities seem to virtually eliminate
such systems from any current application.
Open Cycle MHD Reserve Power Generators
The reserve power use of open channel MHD is uniquely important for two
reasons:
1. Its economic and technical operation is radically different from
574
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base load MUD systems.
2. It will probably be the first commercial application of MUD, pre-
senting an economically convincing case against a backdrop of disappoint-
ment with the technological progress in base load MHD.
Because the MHD process is inherently a low inertia process standby,
generation for short term power reserves can be shown to be economically
very attractive,(W-63) particularly for individual running times less
than 5 minutes and yearly total running times on the order of 50 hours
(200 days with 4 runs of 4 minutes each). The capital costs control
the economics of this system use so the exhaust would be rejected hot
and untreated and represents an anomally in emission considera.tion and
procedures. The fuel is clean and uses oxygen rather than air so the
major pollution concerns would be the seed (probably KSO^) and the hot
gas.
The desire to get practical operating experiences with any kind of MHD
system will bring significant pressure from the technological community
to implement this system.
Open Cycle MHD Base Load Systems
Worldwide interest seems to have focused on open cycle MHD generators
topping steam systems but conflicting reports of Russian experience
with a gas-fired pilot plant designed to produce 25 MV7 from MHD and 50
MW from the associated steam plant have strengthened a European mood
of pessimism.
Research and Development Needs
A significant amount of applied research and practical development lies
between current technology and successful utilization of MHD.
Coal Combustion. To utilize the large reserves of coal with at least 10
percent ash would require sophisticated combustion systems (probably
multistage) that can provide a clean, pressurized, ultra-high tempera-
ture product. Low energy coal gasification techniques, modified for low
hydrogen content because of the MHD electrical process, is an alternative.
Air preheat development probably should be tied to the combustion system.
Channel Materials. Fundamental experience with both insulator and elec-
trode materials in the high-temperature environment with associaced
electrical current flow and slag and seed contamination is crucial.
Improved predictability of MHD channel performance when scaled to prac-
tical sizes is only truly useful with engineering materials so materials
technology is the driving influence.
Seed Recovery and Gas Cleaning. A fortuitous match between seed frac-
tion and coal sulfur content is viewed by some as important. Potassium
carbonate seed seeks out the sulfur in the combustion products to
575
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become potassium sulfate, also an acceptable seed, so when the seed re-
covery process captures about 99 percent of the potassium to avoid an
expensive seed loss, it also has captured the sulfur. Reconversion of
the potassium sulfate to potassium carbonate, beneficiating the sulfur,
is considered straightforward.
Increases of NOX emissions to the level of 10,000 ppm are anticipated
because of the high combustion temperature requirements. Satisfactory
NOX control techniques are considered beyond current and near-future
technology.
Pilot-Plant Studies. Because of scaling problems, some authorities
view the Russian work plan favorably as "...a gigantic experimental
breadboard...(which) will give the Soviet Union an optimum experimental
program1.1. (W-64) Such evaluations are more easily rationalized than
justified. In this paper(W-&4) the author is highly critical of esti-
mates of new exploration for sources of nuclear ore but assumes an
assured fact the ability of the technological community to produce the
advancement's to make MUD practical. MUD development success is not an
assured fact. Eventually pilot-plant studies will have to be considered
in continued MUD research.
Other Variations. Nonsteady flow MUD channel systems may change some
of the critical boundary conditions. Explosion driven and other shock
wave systems have been investigated only far enough to illustrate tech-
nical possibility. At the moment these are only interesting side
issues.
Anticipated Funding. The following tabulation is based on estimates in-
cluding a pilot-plant pro«ram^''~6-O at an aggressive optimum level.
Through 1975 1980 1982
(Millions) 45 300 90
In the estimate, practical development would be completed in 1982 after
a gross expenditure of $435 million for a pilot-plant program returning
$20 million from the sale of power. A net cost of $282.5 million is
estimated(w"64) allowing for residual worth of the plant, presumably
as a production facility.
Environmental Burden. Optimistic assumptions^""^, W-65) are that the
bulk of the new installations of fossil fuel plants after 1985 could be
open cycle MHD/stcam plants assuming a slightly increasing role of fossil
fuel as an electrical energy source and the necessity to retire obsolete
plants.
The environmental emissions arc all gains except for NOX which could be
as high as 10,000 ppm in the exhaust. Of the 10 percent ash entering
with the fuel, at least 75 percent(W-63) wj11 have to be removed in the
combustion process before expansion through the MUD dust. Seed added
576
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at levels of I atom percent must bfi recovered at bcttcr^than 95 per-
cent efficicncy(N-66) to avoid excessive seed costs.
That process will also collect other particulates in the exhaust.
Subsequent seed treatment will renove the sulfur from the coal in the
exhaust (if it was not already removed in a modified combustion pro-
cess) .
Thermal pollution should gain by an overall thermal efficiency gain
from 40 percent to 50 percent. The heat rejection would be reduced
from 60 percent of the thermal energy input to 50 percent.
Closed Cycle MUD Systems
In these systems, noble gases such as helium are heated, seeded, ex-
panded through the MUD channel system, cooled by giving up heat to the
bottoming steam plant (just as in open cycle), cooled in a regenerative
heat exchanger, compressed, reheated by the regenerative heat exchanger,
and recycled to the primary heat exchanger. The working fluid is sealed
from outside contamination and loss.
The primary technological barrier to such a system is the primary heat
exchanger. Steady flow equilibrium ionization of the plasma requires
too high a gas well temperature for any known practical containment
materials. Consequently, phenomenological variations that induce ioni-
zation at much lower source gas temperatures have been proposed. Non-
equilibrium ionization procedures attempt to force local ionization and
rely on tho decay rimp to hold the electrical conductivity through the
MHD duct extraction section. General results to date indicate that,
even when the gas can be tricked into being adequately conductive, other
practical aspects such as density are almost totally mismatched with
practical needs for the rest of the system.
Some, other concepts with shock vaves(w~67> W-68) have been conceived
and have shown preliminary laboratory feasibility but have not been ex-
tended to even bench-scale systems. Research along these lines could
produce MHD/steam systems for application to high-temperature nuclear
reactors where the gases on both sides of the heat exchanger are rela-
tively noncorrosive. Extension of closed cycle operation to combustion
products seems quite unlikely.
Research Experiments. Significant bench-scale experiments at a rate of
$500,000/year through 1975 could establish the feasibility of such a
system. Reduction to practice, however, would' involve pilot-plant de-
velopment at expenditures probably less than for open cycle systems in
about the same time frnme--pilot-plant operation in the early 1980's.
Environmental Burden. The primary impact would be an improvement in the
heat rejection load of nuclear generation plants. If overall nuclear
cycle efficiency can be increased from 32 percent for a representative
light water reactor(w~65) to tnc neighborhood of 45 percent with an MHD
577
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finding new materials capable of high-temperature operation, and at im-
proving the thermoelectric efficiency and general utility of known
thermoelectric materials. Since 1962, the emphasis in thermoelectric-
power generation research has shifted from materials development to hard-
ware development. Improved electrical contacts, improved burners, and
stronger and more chemically stable thermocouples ha\c served to improve
reliability, reduce weight, and bring actual generator efficiencies
closer to theoretically possible values.
Thermoelectric generators have been built and operated satisfactorily
in a variety of situations. They have been operated from heat sources
fueled in many different ways, including butane, gasoline, kerosine,
propane, JP-/i, and fuel-oil burners; radioisotopes; and nuclear reactors.
A large majority of the thermoelectric generators that have been built
have been in the subki]owatt range. Recently the U.S. Atomic Energy
Commission has initiated an Isotope Kilowatt Program which has as its
objective the production of 1 to 10 kw of electrical power for terres-
trial and undersea applications.(W-71) One of the systems being evalu-
ated is a radioisotope thermionic generator (RTG). This program has not
yet progressed to the point where the "best system" has been identified.
Probably the next largest thermoelectric system presently under develop-
ment is the multihundred watt RTG being developed for the space pro-
gram and expected to "fly" in the mid-1970's.(W-72) Presently, the
generator efficiency for the KHW-RTG is expected to be less than a per-
cent. By incorporating a cascading concept, wherein two thermocouples
are in series thermally so that heat rejected by the cold junction of
the first-stage thermocouple is absorbed by the hot junction of the
second-stage thermocouple, somewhat higher efficiencies, perhaps to
nearly 9 percent, can be achieved.
Semiconductors materials used for thermoelectric applications often do
not require the extreme care in preparation that material for devices
such as transistors do. Thus, they may be somewhat less expensive.
Even so the materials cost for thermoelectric elements is still so high
that thermoelectric generators simply cannot compete economically uiLh
other conversion processes. Many experts feel that an order of magni-
tude improvement in figure of merit over those of the best present day
materials would make thermoelectric power generation worthy of con-
sideration for certain applications. There is presently no reason to
believe that a materials breakthrough of this magnitude is likely to
occur in the foreseeable future. Thus, thermoelectric-power genera-
tion is not suitable as an alternative method for large-scale power
generation.
Thermionic Power
A thermionic conwrsion system consists of a heat source, a number of
578
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augmented gas-cooled reactor, the cooling energy released per unit of
electrical energy produced is almost halved.
The effectiveness of MHD systems for meeting possible future demands
for reduction of stack particulates and,sulfur oxides should be con-
sidered high. The cost is inherent and buried within MHD development
costs so the best cost to use would be that of MUD development. Oxide
of nitrogen controls may be relatively ineffective. Since no practical
effective technique has yet been demonstrated, it is difficult to anti-
cipate tiie research costs. As an estimate, about 5 percent of the total
pilot-plant program discussed earlier might be appropriate--$20 million
between now and 1982. '
Thermoelectric
A thermoelectric generator is a device in which a closed electrical cir-
cuit is made up by two dissimilar thermoelectric materials and a load.
Current flows around the circuit when a temperature difference exists
between the two ends of the thermoelectric materials. The efficiency
of energy, conversion depends upon the temperature difference (as in any
thermal "engine"), the device geometry, and a factor involving the
material properties alone. The material factors, called the "figures
of merit", Z, is defined as Z = a2 aK , where is the Seebeck coeffi-
cient, a is the electrical conductivity, and K is the thermal conduc-
tivity.
The quest for higher and higher efficiencies focuses on finding mater-
ials with higher values of Z. Since Z depends upon the temperature,
maximum efficiency for a given material occurs within narrow tempera-
ture ranges.
Prior to 1947, only certain metals were known to exhibit relatively high
Seebeck coefficients. Although the cost of these metals was low, the
efficiencies of electrical power generators using them were only 1 per-
cent at best. In 1947, an article which reviewed the state of thermo-
electric-power generation at that time^"0') showed that materials con-
taining bismuth and antimony, tellurium compounds, and lead compounds
could be used to achieve power-generation efficiencies of about 5 per-
cent. During this same period, the gas-controls industry was conduct-
ing research on thermoelectric generators which' could use the heat from
gas burners and pilot lights to generate the power required to operate
blower controls and automatic controls.(W~70)
The rapid growth in knowledge of semiconductor technology, such as:
control of resistivity, control of purity, methods of materials prepara-
tion, which occurred with the advent of the transistor, along with re-
quirements of the space program, led to heavy expenditures on research
in all phases of thermoelectric power generation. From 1058 to 1962,
the U.S. Navy Bureau of Ships sponsored many research programs aimed at
579
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thermionic diodes, power conditioning equipment, and ancillary tem-
perature control equipment. Major attractive features of thermionic.
conversion systems are the absence of moving parts (which suggests
potentially long service life), a very desirable power-to-weight ratio,
and a good match between the thermal requirements of the diodes and
the capabilities of fast nuclear reactors. These features have made
thermionic power a good candidate for unattended, remote sites, Most
developmental efforts have been directed toward the realization of
systems for such applications.
The most advanced thermionic power generating systems so far developed
have been assembled in the Soviet Union. They have operated thermionic
reactor systems (TOPAZ I for 1500 hours, and TOPAZ II for 6.,000 hours)
at power generating levels of 5 to 10 kwo.(w~73) At the present time
the only major U.S. thermionic program expects to operate a thermionic
reactor system at 50 to 300 kwo power levels in 1978.Cw~73)
Thermionic converters have as the basis of their operation the Edison
effect, that is, the evaporation of electrons from hot bodies. The
number of electrons which are able to escape by surmounting the poten-
tial barrier at the surface of the emitting body is an exponential
function of the emitter temperature. Thus, on the face of it, the amount
of current produced by the thermionic diode should increase rapidly as
the emitter temperature is raised. This behavior would obtain except
for the fact that the first electrons to enter the space surrounding
the emitter exert, as a result of their like electrical charges, re-
pulsive forces on additional electrons attempting to escape from the
emitter. Through this process a space-charge cloud of electrons is
built up in the space surrounding the emitter and the number of elec-
trons then able to escape becomes comparatively small. In order to pro-
vide the high current densities necessary for reasonable efficiencies,
some means of space-charge compensation must be provided.
It is possible to reduce the spacing between the emitting electrode and
the collecting electrode to a small enough value so that space charge
has very little effect upon diode performance. The spacings required,
however, are extremely small, less than 0.001 inch, and the mechanical
problems involved in such a scheme have led to abandonment of efforts
to produce practical, close-spaced coverters.
The alternative method of space-charge compensation that has been almost
universally adopted is the introduction of positive ions into the inter-
electrode space. The usual source of ions is cesium vapor. The ions
can either be produced by surface ionization when cesium atoms come in
contact with the hot emitter, or by volume ionization which occurs in
the interelectrode space as a result of collisions between energetic
electrons and cesium atoms. In practice it has been found that maxi-
mum diode efficiency is achieved when the ions are created by volume
ionization, that is, when the converter is operating in the so-called
arc mode.
580
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As with other energy conversion systems, the efficiency of thermionic
diodes increases as the emitter temperature is -increased. At the pre-
sent technology level there are few materials that can maintain mechani-
cal integrity and hermcticity during atmospheric exposure at tempera-
tures of 1500 C and above. Because of this, the major thermionic devel-
opmental programs have relied upon diode designs wherein the emitter—
i.e., the hottest member—is enclosed in an evacuated space essentially
free from oxygen. VJith such a design one of the obvious ways of pro-
viding the thermal energy to the emitter is to encase nuclear fuel
within the body of the emitter and operate the diode within the core of
a reactor. This concept represents the in-core thermionic power gener-
ator system. All of the continuing major developmental programs are
based upon this concept. ' '
Some attention has been given to out-of-core thermionic systems. A
major accomplishment of these efforts has been the conception and de-
velopment of the heat pipe. These devices have the ability to transport
thermal energy over distances up to several feet with very little ther-
mal loss and to concentrate the thermal flux received over a relatively
large area and discharge it into a much smaller area. Small-scale
fossil-fuel-fired thermionic systems have been developed, some of which
utilize heat pipes and others of which expose the outer shell of the
thermionic diode to the flame. Numerous materials problems remain to
be solved for these systems and at present maximum diode life has been
only a few hundred hours and even then the operating temperatures have
been restricted to values where the conversion efficiency of the diodes
is.only about 10 percent.
One great disadvantage of thermionic converters is that they are low-
voltage high-current devices with typical output voltages of 0.5 to 0.7
volt per cell. Thus, it is necessary to operate a great number of
diodes in series in order to develop normal power-line voltages. Pro-
visions must be made to bypass any cell that might fail in an open cir-
cuit mode and, because thermionic diodes produce direct current power,
a substantial amount of power conditioning equipment will be required
to produce power compatible with existing generating and transmitting
sys terns.
Because of plasma losses, high-temperature materials problems, and lead
losses brought about by the large currents produced in thermionic diodes,
it does not appear that the device efficiency of practical thermionic
diodes is likely to exceed 20 to 25 percent. This conclusion is in dis-
agreement with that reached in Reference W-75 which assumes that even-
tually it will be possible to produce a collector with a work function
of 1.0 eV. Experience has shown that evaporation products from the
emitter deposit on the collector and inevitably lead to higher work
functions after a short period of operation. Projected system effici-
ency of the U.S. system currently under development is of the order of
5 per cent. (W-74_)
The performance characteristics of thermionic diodes probably mean that
581
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they will llnd application as primary systems only when long, unattended
service life, high power- to-weight ratio, or silent operation are more
important than operating costs. On the other hand thermionic diodes
have what is perhaps the unique ability to accept thermal energy at
very high temperatures, up to 2000 C, and reject it at 600 C or above.
This ability would appear to make thermionic conversion highly attrac-
tive as a "topping system" for some other primary system, especially if
the heat source is a nuclear reactor.
The U.S. system presently under development is being supported by appro-
priation of a few million dollars annually. The present schedule calls
for operation of a comparatively low power (40 we) deve.lopmen.tal model
in 1978.(W-73, W-74) There has been a great deal of slippage in sche-
duling on this program in the past, and some slippage probably can be
anticipated,in the future in the absence of increased funding. Reali-
zation of the space-oriented thermionic reactor will have little direct
benefit toward development of a topping system for terrestrial applica-
tions. The technology presently exists for producing a thermionic
topping unit. Some of the discontinued space power developmental pro-
grams appear to have laid much of the groundwork for such a system.
Thermionic diodes are not complicated devices and are not difficult to
produce. Thus, they should not require a large capital outlay once a
suitable system has been developed.
It appears that a demonstration in-core reactor system suitable for use
as a topping unit could be developed by a program similar to the one
now in progress for the space power generator. More detailed analysis
of projected reactor characteristics will be necessary before a meaning-
ful prediction of developmental costs can be attempted. By analogy
to the space power program it seems likely that a small demonstration
thermionic reactor capable of driving a conventional generator might be
developed with an outlay of 20 million dollars over a period of 5
years. Out-of-core thermionic diodes, utilizing heat pipes, which
would be suitable for demonstrating the feasibility of an out-of~core
topping concept probably could be developed and evaluated for a small
fraction of this amount.
Since they would be functioning as a topping unit for other generating
systems, the thermionic diodes would not be expected to have any un-
desirable influence upon the environment. Since they would serve to
increase the overall efficiency of the complete installation, their use
should serve to reduce any undesirable aspects of the primary system.
References
W-l. Mathusa, P. P., and Axelrod, H. J., "Can Urban Power Systems Use
Fuel Cells", Electric Light and Power, E/G Edition, pp 57-59,
April, 1972.
582
-------
W-2. Lueckel, W. J., Eklund, L. G., and Law, S. II., "Fuel Cells for
Dispersed Power Generation", IEE Paper T-72-235-5. Presented at
IEEE Meeting, January 30-February 4, 1972, New York.
W-3. Szego, G. C., "The U.S. Energy Problem", Volumes I and II, ITC
Report C 645, InterTechnology Corp., Warrenton, Virginia, November
1971.
W-4. Hammond, Allen L., "Solar Energy: The Largest Resource", Science,
Volume 177, pp 1088-1090, September 22, 1972.
W-5. NASA, "Solar Power for Terrestrial Use, Twenty-Year Development
Plan", Revision Four, MSFC/PD-SA-0, June 8, 1972.
W-6. Lof, George O.G., et al, "World Distribution of Solar Radiation",
Solar Energy, Volume 10, No. 1, pp 27-37, 1966.
W-7. ASHRAE Handbook of Fundamentals, Chapter 22, p 390, 1972.
W-8. Tabor, H., "Use of Solar Energy for Production of Mechanical Power
and Electricity by Means of Piston Engines and Turbines", Solar
Energy Journal, Volume 6, No. 3, pp 89-93, 1962.
W-9. Air Conditioning, Heating & Refrigeration News, May 8 and 29,
1972.
W-10. Tybout, R. A., and Lof, G.O.G., "Solar House Heating", Natural
Resources, Volume 10, pp 263-326, April, 1970.
W-ll. Tabor, H., "Power for Remote Areas", International Science and
Technology, pp 52-59, May, -967.
W-12. Anderson, J. Hilbert, and Anderson, James H., Jr., "Power From
the Sun by Way of the Sea?", Power, pp 65-66, January, 1965,..and
pp 63-65, February, 1965.
W-13. Anderson, J. H., Jr., "Economic Power and Water From Solar Energy",
ASME Paper 72-KA/Sol-2, November, 1972.
W-14. Runkle, L., "An Evaluation of Technology Needed for Solar Power
for Terrestrial Use", Jet Propulsion Laboratory, SPART report
701-1481, June 23, 1972.
W-15. Farber, Erich A., and Prescott, Ford L., "A 1/4-Horsepower Closed
Cycle Solar Hot Air Engine", ASME paper 64-WA/Sol-5, December,
1964.
W-16. Trayser, David A., and Eibling, James A., "A 50-Watt Portable
Generator Employing a Solar-Powered Stirling Engine", Solar
Energy Journal, Volume 11, Nos. 3 & 4, 1967.
583
-------
W-17. Bealc, W., ct al, "Free Cylinder Stirling Engines for Solar-
Powered Water Pump", ASME Paper 71-WA/Sol-ll, 1971.
W-18. Daniels, F., "Power Production with Assemblies of Small Solar
Engines", ASME Paper 71-WA/Sol-5, 1971.
•
W-19. Glaser, Peter E., "Power from the Sun", Mechanical Engineering,
Volume 91, pp 20-24, March, 1969.
W-20. Walters, Samuel, "Power in the Year 2001, Part 3—Solar Power",
Mechanical Engineering, Volume 93, pp 33-36, November, 1971.
W-21. "Satellites to Relay Solar Energy for Earth Needs", .Product
Engineering, pp 13-14, August 25, 1969.
W-22. Rex, R. W., Geothermal Energy—the Neglected Energy Option,
Bull. Atomic Scientist, pp 52-56, October, 1971.
W-23. Geothermal Energy, A Special Report by Walter J. Hickel, pub-
lished by the University of Alaska, 1972.
W-24. Brown, D. W., Smith, H. C., and Potter, R. M., "A New Method
for Extracting Energy from 'Dry1 Geothermal Reservoirs", LA-DC-
72-1157, Los Alamos Scientific Laboratory, Los Alamos, New
Mexico, p 23, 1972.
W-25. A Feasibility Study of a Plowshare Geothermal Power Plant,
Battelle Northwest Laboratories, Richland, Washington, April,
1971.
W-26. Bowen, R. G., "Electricity fron Geothermal, Nuclear, Coal
Sources", The Ore Bin, Volume 33, No. 11. Publication of Oregon
Department of Geology and Mineral Industries, 1971.
W-27. Hess, Hamilton, "Environmental Priorities, Human Needs and Geo-
thermal Power", in Compendium of First Day Papers presented at
the First Conference of the Geothermal Resources Council,
Geothermal Resources Council, Davis, California, p 77, 1972.
W-28. Brace, W. F., Orange, A. S., and Madden, T. R., J. Geoph. Res.
Volume 70, p 5669, 1965. '
W-29. "Geothermal Wastes and Water Resources of the Salton Sea Area",
California Department of Water Resources, Bull. No. 143-7,
February, 1970.
W-30. Barton, David B., "The Geysers Power Plant—A Dry Steam Geothermal
Facility", First Conference of the Geothermal Resources Council,
Geothermal'Resources Council, Davis, California, p 77, February,
1972.
584
-------
W-31. Bruce, A. W., "Engineering Aspects of a Geotherraal Power Plant",
U. N. Symposium on Geothernial Resources; Pida, Italy, September,
1970.
W-32. Salinos, I. B., "Projects de la Planta Geothermoelectrica Cerro
Pricto", Reunion Nacional de Ingenieria Quimica Aplicada a la
Generacion le Energia Electrica.
W-33. Assessment of Geothermal Energy Resources, Dallas L. Peck,
Department of the Interior, September 25, 1972.
W-34. Joint Committee on Atomic Energy Hearing on Controlled Thermo-
nuclear Research, November 10-11, 1971.
W-35. L. A. Booth, "Central Station Power Generation by Laser-Driven
Fusion", Los Alamos informal report LA4C58-M, Volume 1, February,
1972.
W-36. "The Limits to Growth" by D. H. Meadows, D. L. Meadows, Jorgen
Randcrs, and W. W. Eehrens III, Universe Books, N.Y., 1972.
W-37. W. C. Gough and B. J. Eastlund, "The Prospects of Fusion Power",
Scientific American, February, 1971.
W-38. J. Rand McNally, Jr., Prospects for Alternate Fusion Fuel Cycles
at Ultra-High Temperatures, Oak Ridge National Laboratory, ORNL-
TM-3783, April, 1972.
W-39. II. Postma, "Engineering and Environmental Aspects of Fusion Power
Reactors", Nuclear News, April, 1971.
W-40. D. J. Rose, "On the Feasibility of Power by Nuclear Fusion",
ORNL-TM-2204, 1968.
W-41. Fraas, A. P., "The BLASCON—An Exploding Pellet Fusion Reactor",
USAEC Report ORNL-TM-3231, Oak Ridge National Laboratory, July,
1971.
W-42. Watson, J. S., An Evaluation of Methods for Recovering Tritium
From the Blankets or Coolant Systems of Fusion Reactors, Oak
Ridge National Laboratory, ORKL-TM-39S4, July, 1972.
W-43. Bishop, A. S., "Recent World Developments in Controlled Fusion",
Nuclear Fusion, Volume 10, 1970.
W-44. Fusion for Power, Public Service Electric and Gas Company, 1970.
W-45. Searby, P. J., and Brookes, L. G., Nuclear Fusion Reactor Con-
ference (Proceeding Conf. Culham 1969) BNES, 20, 1970.
585
-------
W-46. Werner, R. W., et al, "Engineering and Economic Aspects of
Mirror Machine Reactors with Direct Conversion", IAEA-CN-28/K-2,
IAEA Conf. on Plasma Physics and Controlled Thermonuclear Fusion
Research, 1971.
W-47. Steiner, D., A Review of the ORNL Fusion Feasibility Studies, Oak
Ridge National Laboratory, ORNL-Til-3222, December, 1970.
W-48. Benedict and Pigford, Nuclear Chemical Engineering, McGraw-Hill
Book Company, Inc., 1960.
W-49. Electric Utility Industry Research and Development Goals Through
the Year 2000, Report of the R&U Goals Task Force to the Electric
Research Council, ERC Pub. No. 1-71, June, 1971.
W-50. Steiner, D., "Emergency Cooling and Radioactive Waste-Disposal
Requirements for Fusion Reactors", IAEA-CN-28/K-11.
W-51. Gray, T. J., and Gashus, 0. K., "Tidal Power", Plenum Press,
N.Y., p 630, 1972.
W-52. U..S. Energy, A Summary Review, Department of Interior, January,
- 1972.
W-53. The U.S. Energy Problem, Volume 1, Summary, National Science
Foundation, November, 1971.
W-54. Melese d'Hospital, G. B., "Factors Affecting the Design of Gas-
Cooled Fast Breeder Reactors", Proc. of the National Topical
Meeting on Fast Reactor Systems, Material and Components, CONF-
680419, April 2-4, 1968.
W-55. Dee, J. B., and Melese d'Hospital, G. B., "Gas-Cooled Fast
Breeder Reactor Designs", Mech. Eng., Volume 28, February, 1942.
W-56. Thomas, W. N., and Simon, R. II., "The 300 MWe Gas-Cooled Fast
Breeder Reactor Demonstration Plant", Volume 33, Proc. of
American Power Conf., 1971.
W-57. Fortescue, P., "Gas-Cooled Fast Breeder Reactor Development",
American Power Conf., Chicago, Illinois, GA-9289, April 22-24-
1969.
W-58. Robertson, R. C., et al, "Conceptual Design Study of a Single-
Fluid Molten-Salt Breeder Reactor, ORNL-4541", June, 1971.
W-59. "Nuclear Applied Technology, Volume 8, February, 1970 (entire
issue)
W-60. "Liquid Metal Fast Breeder Reactor Program Plan", WASH-1108,
LMFBR Program Office, Argonne National Laboratory.
586
-------
W-61. "In Pursuit of the LMFBR", Nuclear News, March, 1970.
W-62 . Proceedings of the Conference on the Constructive Uses of Atomic
Energy, ANS, 1969.
W-63. Bunde, R. , Muntenbruch, H., and Helm, S.-, "The Combustion MUD
Generator as a Reserve Plant in Electricity Supply Systems",
12th Symposium, Engineering Aspects of Magnetohydrodynamics,
Argonnc National Laboratories, March 27-29, 1972.
W-64. Dicks, J. B., "MHD Central Power: A Status Report, Mechanical
Engineering, May, 1972.
i1 -
W-65. Schurf, Sanett, "Energy Research Needs", October, 1971.
W-66. Heywood and Womack, "Open Cycle MHD Power Generation", Pergamon
Press, Oxford, 1969.
W-67. Stingelin, V., "The Non-Steady Flow in a Magnetohydrodynamics
Shock-Wave Generator of Finite Length", Zeitschrift fur
Angewandte Mathematik and Physik, Volume 21, January, 1970.
W-68. Jimevin, et al, "MHD Energy Conversion Using Detonation Condi-
tions", 12th Symposium, Engineering Aspects of Magnetohydro-
dynamics, Argonnc National Laboratories, March 27-29, 1972.
W-69. Telkes, M., "The Efficiency of Thermoelectric Generators",
J. Appl. Phys., Volume 18, pp 1116-1127, 1947.
W-70. Fritts, R., "The Development of Thermoelectric Power Generators",
Proc. IEEE, Volume 51, pp 713-721, 1967.
W-71. Fraas, A. P., and Samuels, G., "Isotope Kilowatt Program
Quarterly Progress Report for Period Ending September 30, 1971.
Oak Ridge National Laboratory Report, November, 1971.
W-72. Hembcr, R. J., Kelley, C. E., and Haley, V. F., "Multi-Hundred
Watt Converter Design Considerations", Proceedings, Intersociety
Energy Conversion Engineering Conference, Las Vegas, Nevada,
September 21-25, 1970, pp 15-1 to 15-7.
W-73. Beard, D. S., and Lynch, J. J., "Thermionic Reactor Program, an
Overview", Conference Proceedings, Seventh Intersociety Energy
Conversion Engineering Conference, San Diego, California, pp
1036-1040, September 25-29, 1972.
W-74. Beard, D. S., "Thermionic Reactor Technology—An Overview", Con-
ference Proceedings 1971 Intersociety Energy Conversion Engineer-
ing Conference, Boston, Massachusetts, August 3-5, 1972, pp 933-
938.
587
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W-75. Szcgo, G. C., The U.S. Energy Problem", Volume II, Appendix U,
p U-8.
588
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APPENDIX X
MISCELLANEOUS ENERGY SYSTEMS
•
Table of Contents
Pace
Summary 590
Hydrogen Energy 592
Space Heating » . 599
Energy Storage Systems 615
Waste Heat Recovery '.'.... ?. 619
References . • 622
List of Tables
X-l. Energy Consumption for Space Heating in U.S. by
Fuel and Sector 601
X-2. Emissions from Residential and Commercial Space
.Heating and Industrial Steam Generation 601
X-3. . Emissions from Residential and Commercial Space
Heating and Industrial Steam Generation 602
X-4. Inventory of Heating Equipment and Fuels for
Residential Space Heating in the United States. . . . 603
X-5. Efficiencies and Emission Factors Used in Residential
and Commercial Analysis 604
X-6. Residential Case 1 606
X-7. Residential Case II 607
X-8. Residential Case III 608
X-9. Commercial Case I 610
X-10. Commercial Case II 611
X-ll. Emission Factors and Efficiencies Assumed for
Industrial Space Heating 613
X-12. Commercial-Industrial Case 614
List of Figures
X-l. Energy Transmission Costs 594
X-2. Relative Costs of Energy by System 594
589
-------
APPENDIX X
MISCELLANEOUS ENERGY SYSTEMS
Summary
Hydrogen energy (and a fuel cell total energy system utilizing hydro-
gen), space heating and insulation, energy storage, and waste heat
recovery were" examined for their influence on the environment. Gen-
erally, these systems have a favorable environmental burden: the
combustion of hydrogen produces little or no burden; the use of in-
sulation diminishes space-heating fuel emissions and conserves energy
resources; energy storage, particularly as compressed gaseous fuel or
as compressed air for turbine power, decreases the environmental bur-
den; and waste heat recovery, where it is economically practical,
diminishes the thermal pollution of streams and air.
The systems are qualitatively ranked as follows:
e Hydrogen energy
9 Space heating and insulation
e Energy storage
« Waste heat recovery.
Hydrogen is a very versatile fuel which is capable of providing large
quantities of electrical and other forms of energy including synthetic
fuels. Until natural gas supplies or comparative costs make hydrogen
economically, competitive, the incentive to move swiftly toward a
"hydrogen economy" is not present, and, therefore, it is unlikely that
significant energy will be developed from this source through 1990.
The assault on the environment caused by producing hydrogen by coal
gasification and hydrogen utilization to produce steam-electric power
is considered to be less than conventional coal-steam-electric plants.
Nuclear power-water electrolysis-produced hydrogen will have little
more environmental burden than the LW nuclear electric plant itself
except for the inefficiencies of electrolysis and reconversion of the
hydrogen to electricity. An important consideration in utilization
of hydrogen is that it will not contribute undesirable emissions at
the point of utilization either as fuel for fuel-cells or for steam
generation when electrolytically produced hydrogen and oxygen are used
as the energy source.
Space heatinR consumes about 20 percent of the nation's energy. En-
vironmental burden from air pollution emission can be effected by
590
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fuels, equipment design, equipment adjustments, and thermal insulation
of the structures.
The analyses presented in this appendix for residential, commercial,
and industrial space heating are based on simplified cases using aver-
age emission factors for different fuel-types in general classes of
equipment. An important consideration that is masked by the use of
averages is the wide difference in emission performance between differ-
ent heating units within a class; in view of this factor, continued R&D
effort is needed to establish criteria for the design, operation, and
maintenance of combustion equipment for minimum emissions.
, j
Improved thermal insulation is one of the most effective, simplest,
economical, and immediate control measures for air pollution emissions
from space heating—and an approach that can be implemented by indi-
vidual home owners.
Hydro-pumped energy storage has proved to be the only practical system
thus far deve'loped to store large quantities of energy recovered from
other systems, but its undesirable utilization of land as reservoirs
is a decided deterrent to its widespread use.
The electrochemical storage of off-peak energy by means of water
electrolysis-fuel cell combinations in which the hydrogen and oxygen
are stored for later use, offer some attractive possibilities. Unlike
hydro-pumped storage, electrochemical storage is not seriously site
restrictive. When used in conjunction with nuclear plants,, electro-
chemical storage of energy would tend to decrease the environmental
burden as compared with pumped storage of fossil fueled plants.
Like natural gas, hydrogen may be stored as compressed gas or by lique-
faction. Though this may be accomplished without serious aesthetic
insult to the environment, the matter of leakage of hydrogen from un-
derground storage and gaseous emissions associated with the combustion
process associated with the compressor prime movers may contribute to
the environmental burden.
Compressed air storage from gas turbine power generating equipment dur-
ing off-peak loads for reuse during peak loads appears to be quite
attractive. The gas turbine will produce only one-third of the com-
bustion products as environmental burden since it is unnecessary to
provide power to the compressor during the period when the compressed
air storage is used. This system has not as yet been utilized exten-
sively, however.
Waste heat is generally regarded as the heat rejected in power cycles,
especially those associated with the generation of electricity. Waste
heat recovery and its utilization to produce useful products, and
thereby unburden the environment, hold very marginal promise economi-
cally. Financial incentives exist in the areas of climate control
591
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(particularly in community total energy systems), agriculture, and
aquaculturc. As higher priority is placed on the conservation of
energy resources, a further enhancement of the benefits from waste
heat recovery are to be expected.
Hydrogen Energy
There is little question but what fossil and nuclear-fission fuels
will be the backbone of our energy sources in the United States for
the remainder of this century. Controlled fusion'is touted; as being
the Utopian energy conversion system of the future but its many and
difficult problems do place it quite into the future. As an inter-
mediate fuel, hydrogen has much to offer:
e It can be produced in huge quantities
relatively economically from various
Ct-l \.'J Y-ll
sources'- L> » '
e It may be transported more economically
than electricity(X~4» X"5^
e It is a low environmental pollution energy
resource^"6'
e In contrast to electric energy, it is
readily storable(x"6)
o It may be put to a variety of uses either
as a fuel for producing electricity or as
a chemical base for a spectrum of synthetic
chemical products X~8'.
Hydrogen, like deuterium and tritium for controlled fusion, is a Uto-
pian fuel, but the significant difference is that the technology for
developing the "hydrogen economy" is well in hand.
Hydrogen as a fuel may be produced by gasification of coal, by elec-
trolysis of water, and from methane and some solid wastes. It can be
transported in underground pipelines much as our natural gas is today.
For distances over 150 miles, hydrogen may be transported less expen-
sively than electricity. The combustion of hydrogen emits no unburned
fragments which are undesirable, although, when air is the oxidizcr,
NOX is formed as with any conventional fuel. Aside from being used
as a fuel, hydrogen can be the basic ingredient of many synthetic
chemicals such as methane, metHanoi, ammonia, and ethylene.
The technology for bringing about the hydrogen economy exists. How-
ever, its cost in terms of equivalent energy is higher than natural
gas today but it could well be competitive in the near future.
592
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Hydrogen Production
The science of producing hydrogen from the fossil fuels is as old as
the significant demands for hydrogen which began at the turn of the
century. By 1968, the United States was generating more than 2 tril-
lion cubic feet of hydrogen annually, with a growth rate of about 18
percent per year/X~9) jjost was produced from natural gas, petroleum
fractions, and off-gases from refineries. Although coke was used
widely two decades ago for generating hydrogen by the water-gas proc-
ess, little coke is gasified now. A strong trend is evident today to
return to coal as the raw material for hydrogen generation as an inter-
mediate in producing substitute natural gas. Several gasific.ation
schemes are now being investigated intensively, with a number in or
approaching the pilot-plant stage.
The average price of hydrogen in 1968 was $0.25 per thousand cubic
feet, with the selling price in 1970 for 95 percent hydrogen ranging
from $0.20 to $0.60 per thousand cubic feet. The projected costs by
1990 will be'between 22 and 30 cents per 1000 cubic feet.(X~^ Plant
size is important, the cost decreasing rapidly up to capacities in the
range of 20 million cubic feet per day. For lowest costs, plant output
probably should lie between 50 and 250 million cubic feet daily. The
production of hydrogen by electrolysis today costs about four times
that from steam-reformed methane.' "' With the developments going on
at the present time, it is expected that costs for producing hydrogen
by electrolysis can be substantially reduced to the equivalent of 20
kwhr per pound of hydrogen with a capital outlay (for the electrolyzer)
of $50 per pound of hydrogen per day.™"*' Without doubt, the large
quantities of hydrogen required tomorrow will come from fossil fuels.
Electrolytically produced hydrogen from nuclear power may be a potential
source in the future.
The efficiency with which coal can be converted into hydrogen depends
greatly on the gasification system. Essentially all the older schemes
are based on coke. Roughly 85 percent of the heat in the original coal
to the coke oven is recovered as coke or useful by-products, but con-
version of the coke to hydrogen will have an overall thermal efficiency
ranging from about 50 percent to 80 percent. Hence, the overall effi-
ciency from original coal to hydrogen could be as low as 30 percent.
Such systems would be unattractive compared with present central-
station power plants with their 40 percent overall efficiency from coal
to electricity. Fortunately, gasification schemes are now being devel-
oped, such as the fluidized-bcd gasificr, that have the potential for
overall conversion efficiencies from coal to hydrogen of 75 percent
with additional recovery of process heat as useful steam.
Hydrogen Transmission and Distribution
Analyses indicate^~^> *~5) that hydrogen can be transported in pipe-
lines for about one-third the cost of electricity and slightly higher
593
-------
than natural gas. The break-even point is for distances of 150 miles;
above this distance, hydrogen has a distinct cost advantage as shown in
Figure X-l. As the hydrogen pipeline will be underground, aesthetic
problems associated with the electrical transmission towers and lines
will be eliminated entirely. Distribution costs will be 4-1/2 times
less than for electricity and slightly higher than for natural gas.
The relative costs for production, transmission, and distribution for
several energy systems are presented in Figure X-2. It will be noted
that the coal gasification-to-hydrogen system offers the best overall
cost attractions for energy produced and delivered to the utilization
point. The costs for underground electrical transmission are about 90
percent greater than shown in Figure X-2.
Hyd
• 70
^ GO
m
l4«
S>to
n
£>b<0
•£»-
0 >-
•TjSao
** "
w£20
£ °
i§ 10
0
Sower: In
rogen pipeline: cheaper transmission at long distances
— .-•—
./
^f9
Ky'dcog1
J^
^
.•*
•
n tranw^
/&
&£[
.'"''"
/
ion ./
____ . ^, T"**',^^*
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* ^^.:?«
. i ••
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• v -~.~^-
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• •
' ^'•'-:
•£~y ;.;.';.•'.'••
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•
•
iO 100 ISO 2CO 250 300 350
Distance from power station, miles
llitulc or Cji Technology.
FIGURE X-l. ENERGY TRANSMISSION COSTS
Hydrogen Energy Storage
Hydrogen, like natural gas, may be stored either as a liquid in tanks
or as a gas in geologically appropriate spent natural gas wells. By
way of comparison, the largest hydro-pumped storage system covers
several acres and produces 15,000,000 kwhr of electrical energy. For
a 50 percent conversion efficiency, a 90-foot spherical tank will con-
tain the equivalent energy of liquid hydrogen.
Because of the variability of wind and tidal power, electricity pro-
duced from such sources may be converted into hydrogen and stored for
later conversion electricity. The storage of hydrogen is presented in
more detail in the section on Energy Storage in this Appendix.
594
-------
A mm
1 ••
0 J.
Nuclear
Electrie(e)
Coal/Steam
Electric
Electrolytic
Hydrogen
KEY
— iDistribution
ESS — iTransmisiion
C23 — iProduction
FIGURE X-2. RELATIVE COSTS OF ENERGY BY SYSTEM
-------
Environmental Burden (at Coal Gasifer Site)
The gasification plants, as long as it is consistent with water supply
needs,* ' should be located as near as possible to the coal mine
since it will be cheaper to move hydrogen than coal. Thus, any emis-
sion will be far from the urban areas in which energy is needed.
Secondly, gasification plants inherently will emit less pollutants than
power plants for at least three reasons: (1) sulfur in the coal will
be converted to hydrogen sulfide which is easily removed from hydrogen;
(2) no large-scale combustion systems are involved, so the NOX produc-
tion will be somewhat lower for a gasification plant; and (3) since
there is no large volume of flue gas carrying off fly ash, "there will
be no output of particulate matter from the gasifier. Overall, there-
fore, a gasification plant should produce much less environmental burden
than a coal-steam power plant. The gasification environmental burdens
are discussed in the fossil-fuel gasification section of this report.
Nonetheless, the water consumption for the gasifier plant is high and
will have a regionally oriented impact on the environment.
If low-cost nuclear energy becomes available in large quantities with
the location of nuclear reactors in remote sites where thermal pollu-
tion can be tolerated or utilized, hydrogen may be produced by elec-
trolysis and transmitted through pipelines much more efficiently than
electricity transmission, thereby unburdening local community environ-
ments (where the hydrogen is utilized) of nuclear reactor pollutants.
Hydrogen Utilization
Hydrogen is ideally suited for direct conversion into electricity in
fuel cells. With a 53 percent efficiency of converting hydrogen to
electricity at high loads, the overall system efficiency from coal to
hydrogen to electricity would be about 40 percent. The waste heat from
the fuel cells may be utilized for comfort control of living spaces. A
suggested overall total energy system utilizing coal gasification to
hydrogen, its transmission, and its distribution to urban-area fuel-
cell substations is included as a supplement to this section.
Hydrogen could be utilized as a fuel in residences without venting in-
sofar as carbon monoxide or carbon dioxide are concerned. Hydrogen
could serve as an ideal industrial fuel as well as provide atmospheric
protection in the ore and metallurgical processing of metals. Hydrogen
is required in large quantities in converting coal into substitute
natural gas.
There are proposals for using hydrogen for high-speed aircraft engine
fuel. Hydrogen provides a good heat sink and extends the range of air-
craft beyond that associated with JP-type liquid fuels. The projected
costs of the two fuels break even in 1985^"^'. Of course, particu-
late and the gaseous emissions (with the exception of NOX), associated
596
-------
with conventionally fueled aircraft engines will be eliminated by the
use of hydrogen fuel. Liquid hydrogen for aircraft will pose special
problems in handling, but these have been solved satisfactorily in
rocket fueling systems.
There are also proposals to utilize hydrogen fuel for reciprocating
engines,(X-13) gas turbines, and for ground transportation vehicles.*
*A, A—LD/
Safety
One of the most important considerations in utilizing hydrogen is one
of safety.* _' Those who are concerned about safety need to be con-
vinced that hydrogen can be used without the disasterous explosions
that occur with the use of natural gas which is less explosive than
hydrogen. The technology exists for handling hydrogen safely and hydro-
gen rich methane gas has been used in the past in the United States
safely. It is also being used in Italy as a fuel containing 80 percent
hydrogen without difficulty.(x~^' Hydrogen dilution is suggested as a
means for providing safety. Hydrogen enriched natural gas may be a via-
ble means for the transition period from natural gas as hydrogen becomes
the primary fuel.
One scheme, which is discussed in the supplement to this section, uti-
lizes hydrogen in a fuel cell substation so that the hydrogen itself is
not utilized within the residences or buildings being supplied with the
electrical energy. If pure hydrogen is to be used with residences, ex-
plosion-proof switches, motors, and telephones may be necessary and
this could increase construction costs by an estimated 10 percent.
From the foregoing it may be seen that hydrogen is indeed a versatile
fuel and one which will produce a minimum impact on the environment at
its point,of utilization. It has the capability of supplying the large
demands for clean energy which will be needed in the future.
It will allow the use of low-grade coal which will not otherwise be
usable because of environmental considerations**"^' but techniques for
gasifying eastern coal still require development.
R&D Requirements
There are a variety of research needs. Chief among them are the pro-
duction methodologies for low-cost hydrogen,(^-10) hydrogen transmission
techniques, and the development of technical and safety standards for
transporting, distributing, and utilizing hydrogen. There have been
some 40 million dollars expended on coal gasification since 1964. Ex-
penditures of the order of some 200 million may be needed by 1985 with
an extra 100 million for the first production prototype plant.
597
-------
Supplement on Total Energy System
Hydrogen Fuel Coll Total Energy System For Urban Communities. One
application of fuel cells is to produce hydrogen in large quantities
from coal as a typical energy source; to distribute that hydrogen by
pipeline to 1-MW fuel-cell underground substations in urban areas in-
tended to serve 40 homes grouped around the substation; to convert the
hydrogen to electricity in conventional hydrogen-air fuel cells and
distribute low-voltage direct current to the surrounding nearby homes
by hollow copper conductors; and to pipe through those same conductors
hot water provided by thermal losses in the substation systems. In
this way, a large fraction of the chemical energy in the hydrogen can
be converted into useful work with no effect on the environment in the
urban area. Water is the sole reaction product from the fuel cells;
the little waste heat produced in the substation can be utilized in
the nearby homes. Any impact of the total system, then, will come in
the remote area where the hydrogen is produced.
A city of 40,000 homes could be supplied with all its energy require-
ments by a thousand such substations. This equivalent 1,000 MW power
system would consume approximately 4.8 x 10^ cubic feet of H2 per day
at constant full-power output. Production of H2 from coal by the most
promising method should recover 75 percent of the heating value of the
coal as H2« This H2, in turn, should be convertible to electricity
with a system efficiency of at least 53 percent, so that the overall
efficiency from coal to the energy used in the household should be 40
percent. Hence, the total impact on the environment will be comparable
to conventional power generation but with all the environmental prob-
lems occurring at the H£ plant and none in the urban area.
No data are in hand on the emission of pollutants from H2 plants based
on fluidized-bed gasifiers now under development of the kind envisioned
here. Since the gasification step will convert sulfur in coal into
I^S, almost completely quantitative removal of sulfur can be achieved
from the product H2. There will be no emission of NO directly in the
gasification step because no combustion takes place. The power plant
supplying the gasification plant with electricity will emit pollutants
like any conventional power plant. But since the amount of electricity
required to run the gasification plant is not known as yet, the amount
of pollutants emitted cannot be estimated. Roughly, if the electrical
input amounted to 10 percent of the energy output of the gasification
plant, the NOX output would be about 10 tons per 1,000 MW per day. No
appreciable quantity of particulates would be emitted, assuming that
the power plant is equipped with electrostatic precipitators.
Overall thermal losses from coal to energy delivered to each residence
would be about the same as for conventional power plants, since both
systems have an overall thermal efficiency of 40 percent. The heat
losses from the two systems, however, would be distributed differently
with the fuel-cell system delivering most of its waste heat to homes
598
-------
where the thermal energy can be recovered usefully, whereas the central-
station power plant discharges its waste heat into the environment.
The urban fuel-cell substation concept is at a very early stage of
technical development. Present-day hydrogen-oxygen fuel cells are
still much too expensive. Although operating satisfactorily in space
missions and in other exotic applications, fuel' cells need a large R&D
effort to lower electrode costs and cell-assembly methods to meet the
demands of commercial exploitation. In addition, the production of
low-cost H2 from coal and the development of pipelines specifically for
H£ transport will require additional R&D. Much of the basic research
has been done already. Mainly needed now are the developmental work
and systems studies that will result in a practical, low-cost, urban
power system free of any emission of pollutants in the urban area.
Full-scale installations should be feasible by 1985 at the latest.
Estimated Funding Effort and Requirements
($1000)
Expenditure Expenditure for Each 5-Year Period Through
to date, ' Beyond
1972 1975 1980 1985 1990 1990
$3,000 $5,000 $25,COO $25,000 ?
Fuel-cell substations will completely eliminate pollution in urban
areas if their energy source is hydrogen. Even waste heat will be
conserved in the idealized system. As far as the urban area is con-
cerned, pollution control will exceed all existing and anticipated
regulations. Pollution will occur at the remote site where the ^ is
generated, but the amount emitted is expected to be small compared
with emission from power plants of the same output. Roughly, pollu-
tion control of such a gasification plant probably will not cost more
than $10 per kilowatt of generating capability at the fuel-cell
substation.
Space Heating
This module describes the environmental burden of space heating appli-
cations as consumers of energy. The focus here is the air pollution
impact of fossil-fuel combustion for space heating at point of use.
The following considerations should be noted:
(a) Impacts of the energy supply and transportation
are not covered in this module.
599
-------
(b) Equivalent electrical energy requirements for
electrical heating are identified so that
electrical heating may be related to the im-
pact of the electrical energy system, including
that at the point of electrical generation and
up-stream in the fuel supply circuit.
(c) Energy for water heating is not included, nor
is cooling with direct fossil-fuel energy,
which is relatively insignificant in volume.
Classes of space heating. Space heating is considered here in the
following classes (although definitions of fuel user categories differ
for various statistical records).
o Residential - single-family dwellings, small
apartments, etc.
0 Small Commercial - stores, apartments, small
office buildings, etc.
e Large Commercial and Industrial - large office
buildings, institutions, factories, warehouses,
etc.
The burdens of these major classes of space heating are covered by
separate approaches in this analysis.
Perspective of Space Heating in Overall Energy
Consumption and Environmental Burden
Energy Consumption For Space Heating. Space heating is of major sig-
nificance in the ration's energy consumption and is estimated to
account for about 20 percent of U. S. energy consumption, or about
12,000 trillion Btu in 1968.^ ' Water heating accounts for another
4 percent. These applications are broken down by sector as follows (in
percent of U. S. consumption):
Space Heating, % Water Heating, %
Residential 11.0 2.9
Commercial 6.9 1.1
Industrial . 2.1 est . .3 est
Total 20.0 4.3
Table X-l shows a breakdown of energy consumption for space heating in
residential, commercial, and industrial applications by fuel or energy
source. Natural gas and oil share almost equally in dominating the
residential and commercial space heating market, but electrical heating
has grown in importance in recent years. Use of coal for residential
space heating has dropped sharply since World War II but is still sig-
nificant in some geographic areas.
600
-------
TABLE X-l. ENERGY CONSUMPTION FOP. SPACE HEATING
IN U. S. BY FUEL AND SECTOR, 1968x
Ash (Noncombustible
Particulate)
9
1
1
5
12
4
36
nil
<1
12
19
21
45
1
1
17
31
25
(a) Emissions by combustion lor energy conversion processes.
601
-------
The term "thermal pollution" is not really applicable in space heating
because all the heat energy ultimately is absorbed by the atmosphere;
however, heat lost in flue gases is not useful energy.
Table X-3 provides a breakdown by major-fuel classes for emissions on
a tons/year basis covering: (a) residential and commercial space heat-
ing, and (b) industrial steam generation.(x"1'^
TABLE X-3. EMISSIONS FROM RESIDENTIAL AND COMMERCIAL f .
SPACE HEATING AND INDUSTRIAL STEAM GENERATION* '
Emi
ssions, 10 W tons per
Commercial &
Residential
Space Heating
Pollutants
Coal
Oil Gas
Products of
Incomplete Combustion
NOX
Fuel
Combustible Particulate
CO
HC
Contaminants
SOX
Ash
0.
0.
0.
0.
0.
0.
10
43
09
07
85
12
0.
0.
0.
0.
1.
0.
11 0.07
03 <.01
04 n
64 0.38
2 n
08 n
vear
Industrial Steam
Generation
Coal
0
0
0
0
3
0
.57
.12
.06
.93
.71
.66
Oil
0.
0.
0.
0.
1.
0.
04
01
01
33
07
03
GPS
0.08
<.01
0.02
0.65
<.01
n
n, emission considered negligible.
Approaches to Emission Control for Space Heating
Emission controls applicable to residential and commercial space heat-
ing equipment are relatively limited, and not all options are univer-
sally available. Control approaches can be classified as follows:
e Fuel switching
-- shifting to a cleaner burning fuel
(coal to gas, or to electrical heat-
ing if only the point of use is considered)
• Replacement of outmoded and poor operating
equipment with modern units
6 Improve burner adjustment and maintenance
—tuning for efficiency and minimum emissions
as the simplest form of "combustion
modification".
o Reductions in energy requirements for fuel
conservation
-- improved thermal insulation
-- temperature control setback at night
or during unoccupied periods
602
-------
— heat recovery of internal loads
For large commercial and irdustrial boilers, additional emission con-
trols can be applicable in the form of various combustion modifications
or of stack cleanup processes (i.e. cyclones, prccipitators, or scrub-
bers). However, these controls are not practical or economical for the
major portion of the nation's space heating load.
Analysis of Emissions From Residential Heating
Table X-4 shows the fuels and types of residential heating equipment as
determined by the 1970 Census of Housing.(x~18) Nearly 70 percent of
U.S. homes have central systems or built-in systems. For purposes of
this analysis, a "typical" single-family dwelling with a control or
built-in system was assumed, and estimates of the relative air-pollu-
tant emissions impact were made for heating this unit with electricity,
gas, oil, and coal.
TABLE X-4. INVENTORY OF HEATING EQUIPMENT AND FUELS FOR
RESIDENTIAL SPACE HEATING IN THE UNITED STATES
(1970 Census of Housing)
Million Housing Units, Heating Equipment for Year Around
• Housing Units
13.82 Steam or Hot Water
28.77 Warm Air Furnace
3.52 Built in Electric Units •
5.88 Floor Wa]l or Pipeless Furnace
3.30 Room Heaters with Flue
3.95 Room Heaters without Flue
Fireplaces, Stoves, or Portable
Heaters
0.58 None
Million Housing Units, House Heating Fuels for Occupied
Housing Units
35.01 Utility Gas
16.47 Fuel Oil
1.82 Coal or Coke
0.79 Wood
4.88 Electricity
3.81 Bottled, Tank, or LP Gas
0.27 Other
0.40 None
603
-------
"Typical Residences"
A typical single-family residence is assumed here as having 1500 square
feet, built to FHA specification,^"19' and located in Washington, D.C.
(where the climate is similar to that at the center of the U.S. popu-
lation, near St. Louis, Missouri, in degree days).
Cases
Three cases were assumed as follows to reveal the effect of combustion
equipment tuning by frequent and competent servicing, plus the effect
of increasing thermal insulation.
Residential Combustion Thermal
Case Equipment Tuning Insulation
I Average Approx. FHA specs
II Well-tuned Approx. FHA specs
III Well-tuned Approx. FHA specs
and additional
insulation and
storm windows
With emission estimates for the various fuels for these 3 cases, the
impact of different mixes can be estimated on a national basis, in-
cluding fuel-use patterns, service, and degree of insulation.
Efficiencies and Emission Factors
Table X-5 shows the overall seasonal efficiencies and emission factors
used in the estimates. Seasonal efficiencies are based on the ASHRAE
Guide' ' plus Battelle's judgment. Emission factors are based on
EPA published factors^ ' and on Battelle field measurements of
emissions from residential heating units.(X-22)
Analysis of the Three Residential Cases
Table X-6, -7, and -8 provide a summary of the three residential cases.
Summary of the Residential Cases for Particulate
The effect of the three cases on particulate emissions, one of the sig-
nificant pollutants, can be seen as follows:
Particulate Emission,
Case Ib/year
Gas Oil
I Average Adjustment 0.8 2.6
II Well-tuned 0.7 2.4
III Well-tuned plus 0.3 0.9
additional insulation
604
-------
TABLE X-5. EFFICIENCIES AND EMISSION FACTORS USED IN
RESIDENTIAL AND CCTOffiRCIAL ANALYSIS
Fuel
Gas
Gas -
well
Oil
Oil -
well
Coal
Unit
Efficiency,
percent
65
tuned 70
65
tuned 70
50
Emission
Factor
Units
lb/10u
cu ft
Ditto
lb/1000 gal
Ditto
Ib/ton
Pollutant Emission Factors
Particulate
5,(c>
5(c)
2.4(0
2.4(c)
20
CO HC NOX
20 5^0 SQ(Z)
15 4(c> 80
-------
•TABLE X-6. RESIDENTIAL CASE I
Assumptions: 1500 oq ft house in Washington, D. C. built to FHA specifications
(The U.S. Energy Problem, Vol. 1)
Heating unit efficiency: electric 1007.
gas 657.
oil 65%
coal 50%
Energy losses:
electric • 0 3tu/yr
gas & oil - 54.1xl06 Btu/yr
coal • 100.5xlO& Btu/yr s. Pollutants
Energy
Input
Heating unit
Useful energy 100.5x10 Btu/yr
Residence
Total heat loss is about
39 Btu/hr sq ft floor area
Heat losses
4
Transmission
-> 81.2xlO<> Btu/yr
.Total 100.5x10
Btu/yr
>>
Infiltration
19.3x10° Btu/yr
Energy
Pollutants (Ib/yr)
Energy Inout Losses Parti-
Fcrm of Energy Input (Untts/vr) (Btu/yr) culate CO HC KOy. SO?
,34_13__Btu, 29,400 Kw hr/yr « "^
( ^ ' Btu/yr) ° ° 0000
/1000 Btu\
GasC"^nrJ '
Oil
Coal
/JA5.
(,
000 Btul 1070 gal/yr ,
(154.6x106 Btu/yr) 54.1x10° 2.6 8.3 0.7 20.9 40.7
23.3 442
606
-------
TABLE X-7. RESIDENTIAL CASE II
Energy
Input
Assumptions: 1500 sq Cc house in Washington D.C. built to FHA specifications
("The U.S. Energy Problem", Vol I)
Well-tuned heating unit:
Heating unit efficiency: Electric 1007.
Gas 70%
Oil 70%
Coal 50%
Cost of tuning: Electric - $0/yr
Gas $10/yr
Oil $30/yr
Coal Not effective
Energy Loss:
Electric = 0 Btu/yr
Gaa & Oil= 43.1xl06 Btu/yr
Coal » 100.5x10$ Btu/yr
Pollutants
-*
•y
Hcatidg Uait
Useful enorgy
Residence
— »
Heat Losses
Transmission
81.2xl06 Btu/yr
"I Total 100.5x10*
r»-Btu/yr
Infiltration
19 ,3xlO& Btu/yr
Energy Pollutants (Ib/yr)
Losses Parti-
T „ / -Byi ^PUt (Btu/yr) culate CO HC NOZ S02
Form of Energy Input (units/yr) ___
01 *
Electric
3413
j Btu> 29,400 KW hr/yr 0
IS J (lOO.SxlO6 Btu/yr)
flOOO BtuN ^.f*"! cu :c/vyr 43.1xl06 0.7 2.2 0.6 11.5 0.09
V^eu ft / (143.6x10° Btu/yr)
. OOP Btu
Coal
N 990 gal/yr
J (l43.6x!06 Bt
^15.500
2.4 4.3 0.6 19.3 37.6
155 23.3
607
-------
TABLE X-8. RESIDENTIAL CASE III
Assumptions: 1500 sq ft house in Washington, D.C.
Well insulated plus storm windows
CThe U.S. Energy Problem", Vol I)
Storm windows: reduce infiltration losses by 50% at cost of $2000
Insulation: reduces transmission losses by 67% at cost of $890
Heating unit efficiency = electric 100%
gas 707.
oil 70%
coal 50%
Beating unit receives regular service of cost of $30/yr oil
$10/yr gas
Service not shown effective in reducing emissions from coal-fired units
Energy loss:
Electric
Gas & oil
Coal
Energy
Input
0 Btu/yr
15.8xlO& Btu/yr
36.8x10° Btu/yr
Pollutants
s
Heating unit
Useful energy — —
_. 36.8xl06 Btu/yr
•••^Hd.
Heat Losses
Transmission
27.1xl06 Btu/yr
Total 36.8xl06 Btu/yr
Infiltration
9.7xl06 Btu/yr
Form of
Energy Input
Electric
Gas
Oil
Coal
Energy
Pollutants (Ib/yr)
Energy Input Losses Parti-
(Units/yr) (Btu/yr) late CO 11C
10,800 KUhr/yr 0
(36.8x10* Btu/hr
,.,
Btu/hr)
SPi
0
0000
IS.SxlO6 0.3 0.8 0.2 4.2 0.03
608
-------
glazing was assumed to reduce the heat loss to 16 Btu/hr per square
foot.
Analysis of the Commercial Cases
Tables X-9 and -10 provide a summary of the two commercial cases, using
emission factors for well-tuned residential heating equipment from
Table X-5. Efficiencies were assumed to be 75 percent; this is higher
than for residential units because higher efficiencies can normally be
expected from larger equipment. Coal firing was not included in the
commercial cases because it was generally precluded from use in small
commercial buildings due to operating labor and maintenance costs.
For commercial structures, there are additional avenues for energy
savings beyond improved thermal insulation. These include heat re-
covery of internal loads that would otherwise be lost, like refrigera-
tion condenser heat for grocery stores. Where the period of occupancy
is limited, some savings can be achieved by control-point setback dur-
ing unoccupied periods. These savings will depend on individual cases.
Analysis of Emissions From Larae Commercial
and Industrial Space Heating
Large commercial and industrial space heating is almost entirely by
boilers supplying steam or hot-water systems, although these boilers
may also supply steam for other purposes like industrial processes,
absorption, cooling, or on-site power.
Package firetube boilers are most prevalent in sizes up to about 500
boiler horsepower (16 x 10 Btu/hr output), frequently with dual-fuel
capability firing either gas or oil; many are capable of automatic un-
attended operation. Larger sizes are mostly watertube-type boilers and
are available to fire gas, oil, or coal (some with multiple fuel capa-
bility). Coal firing with stokers is more common in the larger sizes
where a fulltime attendant is available.
Basis for Analysis
Table X-ll shows overall efficiencies and emission factors assumed for
space heating using typical commercial-industrial boilers. The emission
factors are based on EPA published factor' *' and Battellc studies on
commercial boilers.(x~22) The analysis for this class of space heating
is based on emissions per 10^ Btu output (or energy deliverable for
space heating). Coal firing was assumed to be with stokers for com-
mercial-industrial boilers, because pulverized coal firing is seldom
used except in very large industrial boilers or in utility boilers.
Analysis of Commercial - Industrial Case
Table X-12 summarizes air-pollution emissions based on the assumptions
609
-------
TABLE X-9. COMMERCIAL CASE I.
Energy Requirements and Emissions
Based on Unit of 1000 sq ft Floor Area
and Washington, D.C. Location
Heating unit efficiency: Electric 1007.
Gas 757.
Oil 757.
Coal - not suitable to this application
Energy loss: Electric • 0 Btu/yr ,
A Gas & Oil = 14.8 x 10 Btu/yr
Energy
In ——
i
Heating
Unit
Heat losses
Pollutants
Useful energy
44.4 x 106 Btu/yr
Commercial Space (1000 sq ft)'
.Transmission I
Infiltration
&Make
I Total ^
[ 44.4 x 106
>n 1 Btu/yr
Up Airj
Total Heat Losses: Assume 26 Btu/hr sq ft at design condition
26
Btu
hr sq ft x 1000 sq ft
.
Form of
Energy
Electric
Gas
Oil
» 44,400,000
Energy Input
Units/yr
13,000 kw hr/yr
(44.4 x 106 Btu/yr)
59.2 x 103 cu ft
(59.2 x 10b Btu/yr)
410 gal/yr
(59.2 x 100 Rtll/vr
65 F
Btu/yr
Energy Loss Pollutants (Ib/yr)
Btu/yr Farciculace CO HC NO
0 0 000
14.8 x 106 0.3 0.9 0.24 4.7
14.8 x 106 1.0 1.8 0.24 8.0
lour/i
"2
0
0.0'
15.6
610
-------
TABLE X-10. COMMERCIAL CASE II
Sane as
Commercial I
Except for Improved Insulation and Infiltration Loss
and Washington, D. C. Location
Energy Loss: Electric » 0 Btu/yr
. 'Gas & oil = 14.8 x 106 Btu/vr
Energy
In
Heating Unit
Commercial Space (1000 sq ft)
Reat Losses
Transmission
Infiltration &
Make up Air
Total
27.3 x 10° Btu/yr
Total Heat Losses: 16 Btu/sq ft * Hr at design condition
« 16 x 1000
65
x 4626 x 24
Form of
Energy
» 27,300,000 Btu/yr
Energy Input, Energy Loss,
Units/yr Btu/yr
Electric 8000 kw hr/yr 0
(27.3 x 106 Btu/yr)
Gas
Oil
36.4 x 103 cu ft 9.1 x 106
(36.4 x 10" Btu/yr)
251 gal/yr 9.1 x
(36.4 x 106 Btu/yr)
Pollutants (Ib/yr)
Farticulate CO KG NO SO
^ X £
0 0000
0.2 0.5 0.15 2.9 0.02
0.6 1.1 0.15 4.9 9.5
611
-------
in Table X-ll for different types of fuels.
It should be noted that there are wide differences between grades of
oil within the residual oil classification (e.g. No. 4, 5. and 6
grades), resulting in wide differences in emissions. (X~"J These
differences are especially observed in the case of particulate and in
NOX where the range of fuel-bound nitrogen is broad. The new "low-
sulfur residual oils" (generally containing 1.0 percent sulfur) which
are replacing conventional No. 6 oils have viscosity and other burning
characteristics which place them toward the lighter grades of residual
oil; their emission performance is also more like a No. 4 or light No.
5 oil.
Emission Controls
Other than by fuel selection, applicable emission controls for this
class of equipment are generally in the area of improved adjustments
of combustion parameters or of combustion modification; combustion
modifications like staged combustion, or flue-gas recirculation are
most effective in NOX control. (It should be noted that individual
differences between different burner and boiler designs are broad, and
attention to equipment design criteria is important to emission per-
formance. Such differences often go unnoticed in compilations of
average emissions used for inventory purposes as in Table X-ll.)
For coal firing, particulate control devices are sometimes installed
in the stack. These include cyclones, electrostatic precipitators,
baghouses, and scrubbers—with the first two types being most preva-
lent; a 75 percent removal efficiency is common and is assumed in the
footnote comment in Table X-12. S02 stack gas control processes are
not yet commercially used for this class of equipment; their introduc-
tion will depend on practicability and costs of the system and probably
will follow their successful use on utility size boilers.
Insulation for Energy Conservation
in Space Heating
Improving thermal performance of building construction by insulation is
one of the simplest and most universally applicable methods of reducing
air pollution by reducing energy requirements for space heating and
cooling. With added impetus in view of the overall energy crisis, this
roach is receiving widespread attention by government agencies^ 9»
and by industrial groups. Architects and engineers are urging
greater consideration to building design that will minimize energy re-
quirements. (X'24» X"25>
Many homes and other buildings have low levels of insulation, or no
special provision for insulation. Even modest additions of insulation
can reduce heat losses for space heating by substantial amounts. The
most economical and effective location for adding insulation is in
612
-------
TABLE X-ll. EMISSION FACTORS AND EFFICIENCIES
ASSUMED FOR INDUSTRIAL SPACE HEATING
Pollutant Emission Factors
Emission
Fuel Efficiency Units Particulate CO HC NOX S02
Gas
Dist. oil
Resid. oil
Stoker Coal
75
75
75
65
lb/10 cu
ft(e)
lb/1000
lb/1000
Bal*
lb/ton(f>
6
2 -
12
13
0.5
0.9
10
0.6
0.2
0.3
0.2
45
20
60
6
0.6
43
157 5b(
57(c)
(a) Based on 0.3% Sulfur in No. 2 oil
(b) Based on 1.0% Sulfur in residual oil
(c) Based on 1.5% Sulfur in coal
(d) Based on 10% Ash in coal
(e) Based on Battelle studies (Reference X-8) except S0£ which is based
on (f)
(f) Based on EPA Emission Factors
ceilings where heat losses can be high and costs of insulation relative-
ly low per unit area.
Insulation is most economically installed during initial construction,
but insulation can be added to almost any home and to many commercial
buildings, especially roof decks. Storm windows or other double glaz-
ing, plus weather stripping, can also be added to existing buildings,
with important savings in heat losses both by conduction and by infil-
tration.
Insulation Standards. In response to President Nixon's energy message
to Congress on February 8, 1972, insulation levels required in the FHA
Minimum Property Standards have been tightened to cut maximum permissi-
ble heat loss by 40 percent.(X-26)
0
In terms of "U"-value (heat loss in Btu/hr-ft^-deg F) an uninsulated
wood frame wall gives a "U"-value of 0.22. This can be reduced to 0.05
with full insulation in the frame wall. The new FHA Standards for
home construction are as follows:
"U"-Value
Ceilings 0.05 to 0.08
Walls 0.07 to 0.17
Floors 0.08 to .24
613
-------
TABLE X-12. COMMERCIAL-INDUSTRIAL CASE
Energy losses
Electric =0 ,
Gas & Oil = 330 x 10 B'CU
Coal = 540 x 10& Btu
Pollutant
Energy In_
Heating Plant
Useful energy
109 Btu
Heated Space
Heat Loss
-> 10 Btu
Calculations on basis on 10 Btu delivered to heated space
Energy in
'(units/10 Btu Energy Losses
Uncontrolled -
Pollutant Emissions (lb/10 Btu delivered)
.Form of
Energy Used
Electrical
Gas
Dlst. Fuel Oil
delivered to (Btu/10 Btu
heater space Delivered)
293,000kwhr 0
(1000 x 106 Btu)
1.33 x 106 eu ft 330 x 106
(1330.x 106 Btu)
9200 gal 330 x 106
(1330. x 106 Btu)
Residual Fuel Oil 9200 gal 330 x 10
(1330. x 106 Btu)
Stoker Coal
118,50^ Ib 540 x 106
Par ticu late CO
0 0
8.0 17.
18.4 4.6
110. 8.3
1190 .<*) 593.
HC NO
x
0 0
0.81 60.
1.8 184.
2.8 552.
11.9 356.
so2
0
0.8
396.
1450.
3380.
(a) This emission could be reduced to 300"Ib with control equipment of moderate efficiency.
614
-------
Some industry groups are calling for even tighter standards and are
launching campaigns for increased insulation in new construction and
for installation of added insulation in existing structures.(*-27)
The economic payback in fuel savings is relatively short term (2 to 3
years), and the potential saving in total energy requirements is sub-
stantial.
Energy Conservation and Environment Burden. With "reasonably attain-
able" levels of insulation, energy conservation in residential construc-
tion has been estimated to be 1500 trillion Btu by 1982, or about 14
percent of the projected residential usage for space heating and cool-
ing.
This would be- achieved if (1) 3/4 of new residential units in the dec-
ade have proper thermal treatment, (2) 1/4 of the existing single
family homes arc upgraded in insulation, and (3) 1/8 of all single-
family homes add storm windows and doors. In consumer savings, this
would amount to 17.2 billion dollars over the next decade. Potential
improvements are even greater if more homes are upgraded.
The reduction in air pollution burden of space heating is roughly pro-
portional to energy savings from improved thermal performance.
•
This is an area where there can be effective EPA answers to the citi-
zen's question "What can I do to help in environmental protection?"
Energy Storage Systems
Hydro-Pumped Storage
Pumped storage has turned out to be the only practical way of utiliz-
ing off-peak power at a later peak-demand period. Combination pump-
turbines move water from a low elevation to a higher one during periods
of low demand for electricity, and then utilize this head to provide
electricity whenever demand exceeds normal generating capacity.
Environmental Burdens. The main objection to pumped storage comes from
local residents who dislike the appearance of storage reservoirs where
there may be a difference of 75 to 100 feet in the water level between
full and empty. In some places, as in a Colorado installation, the
upper pool is in a remote area. But, as has occurred in New York,
local residents have succeeded in blocking a pumped-storage system al-
most entirely for aesthetic reasons.
Other than appearance, a pumped storage system can have a minor impact
on the local environment because it forms a huge pond with a variable
shoreline. More importantly, since about 4 kwhr input as pumping power
to a storage pond produces only 3 kwhr output, ^there is a net loss of 1
kwhr for every 3 kwhr recovered. (One source(x~2&) suggests an even
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poorer efficiency; 3 kwhr of pumping for each 2 kwhr of energy gener-
ated.) If the input energy is provided by a full-powered steam plant,
then the total emission of pollutants increases 33 percent for that
fraction of the energy that is stored. On this basis, for each 1,000
MW day of recovered electricity, the environmental burden would be 1.3
times that of the generating plant.
Restrictions on the further use of pumped storage will be for aesthetic
rather than technical reasons. Presently operating pumped-storage
plants have demonstrated the practicality of this system of energy
storage. The required head between upper and lower pools and the design
of the turbine pumps have been evaluated thoroughly, as well as the eco-
nomic factors influencing the size and the location of pumped-storage
systems. No further R&D is required, the future extent of pumped stor-
age being fixed mostly by geographical considerations and by economic
factors influencing the ratio between base load and swinging load gen-
erating plants.
Electrochemical Storage
Electrochemical storage of off-peak energy might be used in a manner
similar to pumped hydro storage. Conventional storage batteries, ad-
vanced battery concepts, and water electrolysis-fuel cell combinations
(with storage of hydrogen and oxygen gas) are being considered for use
by the electric utility industry. Electrochemical energy storage
could be used at the substation level (10 MW) close to the load centers
with some savings in electrical transmission cost compared to pumped
hydro storage and peaking systems. Capital costs for electrochemical
energy storage would have to be competitive with pumped hydro ($100-
$150/kw) and achieve similar overall efficiency of 65 to 70 percent.
Environmental Burden. The use of electrochemical energy storage would
provide an increase in pollution level at the central station propor-
tional to the inefficiency of energy storage as for pumped hydro
storage. However, the added pollution load (atmospheric, thermal pol-
lution) would be more uniformly distributed over 24 hours. Elimination
of older inefficient fossil-fueled plants might be achieved by increased
use of energy storage. Reduced atmospheric pollution would be realized
by energy storage in combination with nuclear plants that are most
economic at high load factors. Whereas, pumped hydro has limited appli-
cability because of lack of suitable sites that are technically and
environmentally acceptable, there would be no such limitation on the
use of electrochemical energy storage near load centers.
Since there is presently a large installed electric generating capacity
to meet variations in load (~50 percent load factor for the United
States), up to 25 percent of the U. S. capacity could be electrochemical
energy storage if an economical system were available.
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Hydrogen
A great many comments have been made recently relative to a "hydrogen
economy" and an overview is provided in this Appendix. Here the stor-
age of hydrogen is discussed. Most of these are based on the clean-
burning characteristics of hydrogen where water is the main product of
combustion. But, since air is usually the oxidizcr, appreciable
amounts of NO may also be formed if the hydrogen is burned in conven-
tional equipment. Fuel cells or low-temperature catalytic combustors
will eliminate the NO problem with hydrogen systems, but both of these
energy-conversion devices will require a great deal of development be-
fore they reach large-scale acceptance.
A major advantage of hydrogen is that it can be stored in exactly the
same fashion as natural gas--usually in selected underground forma-
tions from which natural gas has been taken. Like natural gas, or a
tank farm storing residual fuel oil, or even a coal stockpile, such an
underground formation does store energy but in a form which must be
converted into electricity or shaft horsepower or heat. Nothing in
the characteristics of hydrogen make it superior as such an energy
storage system except that it can be produced by electrolysis of water
by off-peak electricity, and hence it has all the attributes of pumped
storage. Electrolysis is, presently, neither low cost nor highly effi-
cient, but if the nuclear power plants of the future must be operated
as base-load stations, then electrolysis may one day look more attrac-
tive economically than it does today.
As far as storage characteristics are concerned, hydrogen h'as two
properties that make it less desirable than natural gas--its low mo-
lecular weight that favors diffusion through underground formations
that can hold natural gas with few losses, and its low calorific value
of only 330 Btu/ft . Hence, volume wise, a storage system based on
hydrogen would have one-third the capacity of the same system with
natural gas. Storage of hydrogen in liquid form almost of necessity
will require the construction of special storage reservoirs because of
the very low temperature of liquid hydrogen,—253 C.
Hydrogen, then, can be stored like other gaseous fuels, and with some
advantages and some disadvantages compared with other energy sources.
Since it provides a highly reactive fuel, relatively easy to convert
into useful forms of energy, hydrogen in some respects is superior to
natural gas, residual fuel oil, and coal, all of which are easier to
store than hydrogen. A major advantage of hydrogen is that it can be
produced readily from off-peak electricity, but at a penalty both in
dollars and in efficiency that may well limit its wide use.
Environmental Burden. The environmental burdens are very similar to
those associated with underground storage of natural gas (Appendix F)
leakage hazards, and combustion pollutants associated with gas com-
pression equipment prime movers.
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Compressed Gas
Compressing air during off-peak hours, and expanding the air through
energy-recovery systems during maximum demand, is a promising, though
little developed, energy-storage process. Using natural underground
formations appears preferable cost-wise to building pressurized tanks
of the required size.
(X-
A unique system involving a gas-turbine has been described by Harboe
29) in which air stored under pressure in a gas-turbine cycle at one
time utilized later in the combustion/expansion part of the cycle. The
air may be compressed using electricity generated during off-peak hours.
ID this fashion, utilizing this stored air, the gas turbine can produce
as much as three times more power than if it had to drive its compressor
during send-out.
Cost-wise, such air storage systems should be appreciably less expen-
sive than other systems in meeting peak-load demands, where output is
demanded for less than 3000 hours per year. According to Harboe's
analysis, send-out costs for air storage are about the same as for
pumped storage at 3000 hours per year at 6 mills/kwhr. For lesser
operating hours per year, air storage costs remain nearly constant at
about 6 mills while other conversion systems become much more expensive.
Environmental Burden. Effects in the environment attributed to the gas-
turbine part of this storage system would be only a third that if the
gas turbine also compressed its combustion air. The total environmental
emission would depend on the system providing off-peak electricity.
Thermal Storage
No suitable means has yet been developed for storing useful amounts of
thermal energy. Most advances have been made in residential solar-
heated homes, where surplus heat stockpiled in beds of gravel or in
Glauber's salt can provide heat for short periods of sunless days.
Other materials with a high heat of fusion or which undergo a phase
change at useful temperatures have been proposed, but a completely sat-
isfactory system has yet to be devised. For residential heat storage,
huge beds of gravel filling what normally would be basement space have
proved to be most practical for storing heat provided by air circulating
through solar-heated collectors on the roof of a residence.
Little opportunity exists for devising a practical system for convert-
ing such thermal energy into electricity or shaft horsepower, largely
because the Carnot-cycle efficiency will be low for the moderate maxi-
mum temperature of the working fluid reached in most heat cycles.
Utilizing halogenated hydrocarbons or such fluids as butane and propane,
thermal storage to be used later makes more sense, but the costs are
expected to be high. The field of thermal energy storage has been ex-
plored quite thoroughly. In general, it appears to have little promise
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if the eventual goal is to generate electricity or mechanical output,
Waste Heat Recovery
Because of thermodynamic limits on the efficiency with which heat
energy can be converted to work energy, electrical power generating
stations must create more heat energy than the electric power they
produce. The unused heat must then be disposed of, presumably to a
water body or to the atmosphere. For example, a modern nuclear power
generating station operates with an efficiency of approximately 32
percent. For every unit of electrical energy produced, two units of
heat energy are discarded as waste heat. Although the thermal impact
of this waste heat on the environment can be a significant problem,
the concept of waste heat recovery is not directed at reducing the
effect of waste heat on the environment but rather at making better
use of this great energy resource.
finding uses for waste heat is not as easy as it might first appear.
The temperature of the waste heat from the power plant is often as low
as 80 to 100 F. There are not many processes that can make productive
use of temperatures this low. In a sense finding uses for waste heat
is nearly equivalent to finding means of beating the Second Law of
Thermodynamics. As a result many of the more promising applications
of waste heat are closely associated with biological comfort rather
than mechanical or chemical processes.
Consideration of waste heat recovery should not be restricted to those
processes which can only make use of temperatures in the 80 to 100 F
range; however, waste heat can be rejected from the power station at
higher temperatures in the form of low-grade steam. Although this re-
sults in a poorer-efficiency for electrical power generation, the
benefits from the process and the electrical power generation may in a
combined sense have made better use of the energy resources. On what
basis should a use of waste heat be considered sufficiently productive
to be employed? In the present system, the yardstick is purely finan-
cial. Unfortunately, the present economic system probably places too
low a value on our limited energy resources. If a national energy
policy were to place higher priorities on better utilization of fuel
resources, many more uses of waste heat could be more readily justified
than are possible today using financial criteria.
A number of the uses of waste heat that have been investigated are
presented in the following paragraphs:
Central Heating and Air Conditioning
The use of low-grade steam for heating residences and stores has been
employed in some cities for a number of years. Since the steam can
619
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be transported economically for only a few miles, the practical use of
steam for central heating requires proximity of the power station to a
large population. Conversely, the potential environmental effects of
nuclear and fossil fuel plants encourage more remote siting. Air con-
ditioning through the absorption process can also be a practical use
of low-temperature steam. This use can be particularly effective in
reducing electrical power needs in regions controlled by summer demand.
Some investigation has been performed on "new city" concepts inten-
tionally designed around small nuclear power plants in order to provide
heating and air conditioning. An underground reactor in a suburb of
Stockholm, Sweden, is used for residential heating in this manner.
On a smaller scale "total energy systems" should be considered as a
productive use of waste heat for central heating. A completely en-
closed community has been designed for Alaska which is the ultimate
extrapolation of the total energy concept.
Water Treatment
Combined power generating stations and desalination plants have been
given a great deal of attention. Bolsa Island, a proposed nuclear sta-
tion of this type, was eventually dropped because of financial consid-
erations. This use of waste heat does hold promise for the future,
however, either in the production of drinking water or water for irri-
gation. Similarly, the use of waste heat has been suggested for sewage
and waste water treatment. Distillation can be employed to separate
the water from contaminants in the waste water. It has also been sug-
gested that heating of sewage can be used to speed up the biological
processes of waste treatment.
Industrial Processes
Few chemical or mechanical processes can make use of very low-grade
heat. There are, however, applications for process steam extracted at
higher temperatures that should be considered as a use of waste heat.
The Dow Chemical Company will make use of steam extracted from a nucle-
ar power plant under construction in Midland, Michigan, for the produc-
tion of chemicals. A similar arrangement is planned in Germany at the
BASF plant.
Agriculture
Some of the more promising uses of waste heat are in the area of agri-
culture. Waste heat can either be employed to extend the growing
season for plants or to improve production by maintaining temperatures
close to the optimum for growth. Water, used for both irrigation and
heating, can be sprayed over the plants or used to heat the soil through
subsurface pipes. Investigation of these techniques is underway in the
Pacific Northwest. Waste heat can also be employed in the heating and
cooling of greenhouses for the production of high value crops.
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In a similar fashion the heating of animal shelters has been suggested
as a means of decreasing feed consumption and increasing productivity.
The effects of climate control on poultry and swine productivity have
been studied and the results indicate that significant improvements
can be achieved. To be practical, however, farms would have to be lo-
cated within close proximity to the power stations. Furthermore, even
if all of the swine and poultry in the country were to be grown in this
fashion it would represent a usage of only a few percent of the avail-
able waste heat from electrical power production.
Aquaculture
Aquaculture represents another promising application of waste heat.
Growth rates for many fish, crustaceans and shellfish are quite temper-
ature dependent and productivity can be greatly improved by maintaining
temperature control. There are a number of successful commercial demon-
strations of aquaculture which include catfish, trout, shrimp, and
oyster production. A classic example of the use of waste heat is pro-
vided by the commercial production of oysters in Long Island Sound in
the effluent of the Long Island Lighting Company. This example also
shows the potential conflict between aquaculture and preservation of a
natural environment. Recent state environmental protection laws limit
power plant effluent temperatures to below the temperatures of value in
promoting oyster production. Once again degradation of the natural en-
vironment must be weighed against the productive usage of energy.
Miscellaneous Waste Heat Recovery Uses
A number of diverse uses can be identified for waste heat. Often these
uses involve a very small fraction of the available energy or have very
restricted application. For example, it has been suggested that waste
heat be employed in clearing snow from city streets or the runways of
airports. Low-temperature steam also has been proposed as the motive
force for urban mass transportation systems.
In conclusion, waste heat recovery as a means .of better utilizing our
energy resources does hold some promise particularly in the areas of
heating and air conditioning, agriculture and aquaculture. There are
only a few examples where a clear financial incentive exists to exploit
this energy resource in today's economy. A more realistic assessment
of the value of our fuel resources to future generations would, how-
ever, indicate the need for more efficient use -of these resources and
would enhance the benefits to be gained from waste heat recovery.
621
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References
X-l. "Hydrogen Fuel Use Cells for New Source", Chemical and Engineer-
ing News, pg 16, July 3, 1972.
X-2. Linden, H. R., "The Hydrogen Economy". J. of Fuel and Heat Tech-
nology, p 17, November, 1971.
X-3. Gregory, D. P., and Wurm, J., "Production Distribution of Hydro-
gen as a Universal Fuel", Proc. 7th Intersociety Energy Conver-
sion Conference, September, 1972.
X-4. "Hydrogen: Likely Fuel of the Future", Chemical and Engineering
News, p 16, June 26, 1972.
X-5. Martin, F. A., "The Safe Distribution and Handling of Hydrogen
for Commercial Applications", Proc. 7th Intersociety Energy Con-
version Conference, September, 1972.
X-6. Gregory, D. P., "Energy from the Ocean", American Gas Association
Monthly, June, 1972.
X-7. Linden, H. R., "Is Our Environment Really Doomed?", American Gas
Association Monthly, Vol 53, No. 6, p 16, June, 1971.
X-8. "Hydrogen Fuel Economy: Wide Ranging Changes", Chemical and
Engineering News, p 27, July 10, 1972.
X-9. Meadows, P., DeCarlo, J. A., "Hydrogen", U. S. BuMines Bulletin
650, 1970, p 97-109.
X-10. Goldbergcr, W. H., "The Union Carbide Coal Gasification Process,
Status of the Development Program", Fourth Synthetic Gas Sym-
posium, Chicago, October 31, 1972.
X-ll. Ertel, C. M., & Metcalf, J. T., "New Fuels-Old Coal", Mechanical
Engineering, March, 1972, p 25.
X-12. Witcofski, R. D., "Potentials and Problems of Hydrogen Fueled
Supersonics and Hypersonic Aircraft", Proc. 7th Intersociety
Energy Conversion Conference, September, 1972, p 1359.
X-13. Weil, K. H., "The Hydrogen I. D. Engine - Its Origins and Future
in the Emerging Energy Transportation-Environment System", Proc.
7th Intersociety Energy Conversion Conference, September, 1972.
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