NERC-LV-539-7
               THE NERC-LV BURNER-
           A MONITOR FOR RADIOACTIVITY
                  IN NATURAL GAS
                        by
                 John L. Connolly
            Environmental  Surveillance
      National Environmental  Research Center

       U.S. ENVIRONMENTAL PROTECTION AGENCY
                Las Vegas, Nevada
             Published February 1973
This surveillance performed under a Memorandum of
          Understanding No. AT(26-l)-539
                     for the
          U. S. ATOMIC ENERGY COMMISSION

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This report was prepared as an account of work sponsored
by the United States Government.   Neither the United States
nor the United States Atomic Energy Commission, nor any of
their employees, nor any of their contractors, subcon-
tractors, or their employees, makes any warranty,  express
or implied, or assumes any legal  liability or responsibility
for the accuracy, completeness of usefulness of any infor-
mation, apparatus, product or process disclosed, or repre-
sents that its use would not infringe privately-owned rights.
  Available from the National  Technical  Information  Service,
                U.  S.  Department of Commerce,
                    Springfield, VA.  22151

          Price:  paper copy $3.00; microfiche $.95.

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                                                         NERC-LV-539-7
             THE NERC-LV BURNER-
         A MONITOR FOR RADIOACTIVITY
               IN NATURAL GAS
                     by
              John L. Connolly
         Environmental Surveillance
   National Environmental Research Center

    U. S. ENVIRONMENTAL PROTECTION AGENCY
              Las Vegas, Nevada
          Published February 1973
This project performed under a Memorandum of
       Understanding No. AT(26-l}-539
                   for the
       U. S. ATOMIC ENERGY COMMISSION

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                               ABSTRACT

An air-aspirated natural gas combustion/condensation system has been de-
veloped for remote location monitoring for radioactivity in natural  gas
through measurement of tritium.  Water of combustion is collected and
analyzed for tritium by liquid scintillation techniques in use at the
National Environmental Research Center-Las Vegas.   This system has operated
well for estimated ambient temperatures ranging from -20°F through +140°F.
Successful absolute tritium concentration determinations have been made for
contaminated natural gas with known amounts of tritium.  One system has
operated with no major malfunctions for a year-and-a-half near the Gasbuggy
site, located sixty miles east of Farmington, New Mexico.

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                           TABLE OF CONTENTS

                                                                     Page
ABSTRACT                                                              1
LIST OF TABLES                                                        111
INTRODUCTION                                                          1
SYSTEM DESCRIPTION                                                    2
OPERATING THEORY                                                      3
OPERATING EXPERIENCE                                                  6
CONCLUSION                                                            8
REFERENCES                                                            11
APPENDICES
     A.  Tritium Concentrations in Natural  Gas -
         Project Rulison                                              12
     B.  Burner Component Drawings                                    17
DISTRIBUTION

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                              LIST OF TABLES


Table                                                            Page

1.    Tritium Concentrations in Rulison Gas from Various          8
      Monitoring Methods.

A-l.   Tritium in Natural Gas - Project Rulison                    14
                                   m

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                             INTRODUCTION

Projects Gasbuggy and Rulison were designed to experimentally test the
feasibility of the concept of underground nuclear stimulation of natural
gas production.  The low permeability rocks of the Lewis Shale formation
and the Mesa Verde formation were extensively fractured by these two nuclear
tests.  This fracturing was intended to allow increased gas flow from these
rock formations.

The use of nuclear explosives, however, imposes restrictions on the use of
the gas.  The inherent radioactivity associated with these detonations
requires that a time interval for radioactive decay be allowed before
producing the gas, and that the gas be continuously monitored when
released.  Producing wells in the surrounding area were also monitored
to determine if the underground fracturing provides a path for radioactivity
to move to their source volume.

To meet this monitoring requirement, the National Environmental Research
Center-Las Vegas (NERC-LV)* developed and field tested a system to continu-
ously burn natural gas at the sampling location and collect the combustion
water for tritium analysis.  Until development of the burner system, meas-
urements were being made of the radioactivity in both the experimental well
gas and, in the case of Gasbuggy, in the production gas from surrounding
wells by filling high-pressure bottles and shipping them to the NERC-LV
for analysis ^  .  Tritium analysis was performed on free water collected
                                                                      (1   o)
with molecular sieve used to dry the gas during the sample collection v '  ',
Gas analysis was accomplished either by open flame combustion  ^ ' or by
oxidation over hot copper oxide; the combustion water collected in both
                                                                 (2)
cases was prepared for liquid scintillation counting for tritium x  .
*At the time this work was performed, the Center was named the Western
Environmental Research Laboratory.

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 However, the pressure  bottle methods used were expensive and cumbersome,
 and provided sampling  only  at  specific points in time.  The burner system
 to  be described  requires  no power and provides unattended, continuous
 sampling in  remote  locations with only periodic attention for collection
 of  the condensate samples.  The condensate sample still needs to be sent
 to  the NERC-LV for  tritium  analysis; however, a complete electronic tritium
 assay system is  currently being built which will provide recorded data at
 the sampling location  while requiring even less attention and no sample
 shipment.

                          SYSTEM DESCRIPTION

 The burner system is a combustion chamber with a condensation column exhaust
 and control  units,  as  outlined in Figure B-l of the attached burner compo-
 nent drawings.   The gas inlet flow is controlled with a pressure regulator,
 the optimum  operating  pressure being determined by the orifice size in the
 aspirator and the size of flame produced in the combustion chamber.  An
 excessive flame yields a  high condenser temperature and low condensate
 collection efficiency.  For gas pressure higher than 30 psig, double pres-
 sure  regulation  is  recommended for smooth gas flow.

 The  aspirator is a  Prest-0-Lite* model  402 mixer with a #2 torch, cut and
 threaded to  fit  the combustion chamber.   The orifice used is determined by
 the  composition of  the gas  to be combusted.   Additional holes were drilled
 into  the aspirator  body to allow greater flexibility in mixture control.
Air aspiration is a fairly critical  function, which is somewhat sensitive
to  interfering parameters such as the gas composition, associated water,
and dirt.  Initial  operation was not without problems; for example, the
Project Rulison gas assayed initially as high as 47 percent carbon dioxide,
and high contents of free water and  a heavy sludge    .  Since the carbon
dioxide fraction  is also responsible for some air aspiration, the orifice
configuration had to be changed as the  carbon dioxide content of the gas

*Registered trademark

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decreased.  As long as correct mixtures were obtained,  no  combustion
problems occurred as a direct malfunction of the aspirator.

The burner section is made from 1-inch inside diameter  stainless  steel
pipe, flanged near the middle to accommodate a fire screen (Figure B-2).
The line carrying the combustible mixture from the aspirator enters the
bottom of the burner section.  The lower section of the burner assures
complete air-gas mixing, and the diffusion screens allow even burning
over the entire fire screen surface to reduce the height of the hot com-
bustion region.  A spark plug igniter, shown as a dashed circle in the
drawing, was installed approximately 1 inch above the fire screen.

The condenser section, shown in Figures B-3 through B-6, is made  from
copper tube 1-1/4 inches inside diameter and copper sheets four inches
square.  All the cooling surfaces are made to take advantage of vertical
convection cooling in addition to radiative cooling.  The  condenser is
mounted within the incline angle limits shown to allow condensate flow  to
the outlet without restricting the exhaust flow.  Additional condensing
surface is provided in the secondary section by inserting  a copper sheet
with a tight, slide fit.

                           OPERATING THEORY

Quantitative use of the burner system depends upon the concept that the
true combustion properties of the air/gas mixture follow the classical  com-
bustion equations for the assayed components of the gas mixture.   For  example,
an assay of the Rulison gas (February 10, 1971) indicated  the following com-
ponents:  *• '.

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              N2                              0.4%
              C02                            22.5%
              H2                              7.0%
              CH4                            65.8%
              CpH/-                             3.2/&
              C.HQ                             0.79%
               o o
      Heavy Hydrocarbons                       0.4%
      Water Content                      No value given

 The  free  nitrogen and  the  carbon dioxide are  non-combustibles.  The heavy
 hydrocarbons  were neglected and an oily sludge material was taken out with
 associated water in  a  trap ahead of the burner.  These components of the
 natural gas may be disregarded for the  intent of this paper since they are
 either  a  very small  fraction of the total, or would normally be removed
 for  consumer  use.  The combustion equations,  then, for the remaining com-
 ponents are:
                                          2H20
             2C2Hg   +   702  - * 6H20  + 4C02

             C3H8    +   502  - * 4H2°  + 3C02

Calculating on a molar basis and correcting for the assay composition,
one liter (STP) of dry natural gas will yield 1.2 milliliters of water.
Any water vapor remaining in the gas would be included as an addition to
the water of combustion.  A direct conversion of radioassay data from a
condensate sample will give the tritium activity associated with the dry
natural gas on a unit volume basis.

The indicator of residual radioactivity in the gas for both the Gasbuggy
and Rulison events was tritium, produced by neutron activation and the

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fission process.  Being a molecular constituent of the natural  gas and
the ground water, underground movement of these compounds can be monitored
without regard to preferential absorption or natural filtration such as
might be noted for other radionuclides produced by the events.   Combustion
of the natural gas and condensation of the exhaust water into a sample for
tritium analysis, then, allows a valid means for detection of underground
movement of the contaminated gas and water to nearby clean production wells.
The liquid scintillation procedures v ' used at the NERC-LV yield minimum
                                                                   (n\
detectable activity (MDA) values of 400 pCi/1  for tritium in water v  ' ;
and, depending on the background count statistics at the time, the MDA
may be well below this.  The MDA for gas having the assay indicated above
is less than 500 pCi/m3.  Having no specific guidelines for maximum allowable
tritium concentration in natural gas, one might compare the monitor system
sensitivity to the guideline for tritium in air of 6.7 x lQk pCi/m3 in
general population areas *  .   Hence, with the ability to detect two
orders of magnitude below this concentration, the burner system is con-
sidered to be very suitable for natural gas monitoring purposes.

Since the exhausted gases are saturated, but at a lowered temperature, some
of the combustion water is certainly lost and only a fraction of the total
production is collected.  The basic assumption used in consideration of data
from the burner system is that no isotope effect or tritium partition will
be noted; the condensate water will have the same tritium concentration as
the total water produced by combustion.  Some published data indicate that
this is not entirely true, that an enrichment of up to about ten percent
may be seen at the temperatures considered for the condenser    .   However,
tabulated data comparing the burner system with two other measurement
methods (Appendix A) show that the burner results are within a few percent
of matching the best available values for tritium activity in the Rulison
gas ^  .  Had correction been made for more recent gas composition assays,
the burner data would more closely align to those data from the other
methods.  In the final analysis, it is felt that isotope effect may be dis-
regarded for general use of the system.  Other influential parameters such

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 as  dilution  by  atmospheric moisture and activity contribution from atmos-
 pheric  tritium  are  thought to have more questionable effect on the data.

                        OPERATING EXPERIENCE

 As  mentioned above,  two units were built by the NERC-LV and fielded for
 use at  the Gasbuggy  and Rulison sites.  However, the uses of the two units
 were different  enough to warrant separate discussion.  A burner was
 operated  at  the Gasbuggy site first, due to the existing gas sampling pro-
 gram there.   At the  time of completion of the first unit, gas sampling
 involved  monthly collection of gas at two points on trunk lines serving
 wells in  close  proximity to the Gasbuggy experimental well.  The samples
 were then sent  to the NERC-LV for analysis.  This was done to assure the
 Atomic  Energy Commission, El Paso Natural Gas Company (EPNG), and the
 State of  California  that no radioactivity was present in that gas being
 distributed  to  consumers in southern California.

 The  initial  purpose  for the burner installation at the Gasbuggy site was
 two-fold; an  extended operational/lifetime test of the unit, and a com-
 parison of the  burner data at the background level to the pressure bottle
 data were needed.  The burner proved successful on both points.  The burner
was  installed at the production line sampling point early in October 1970,
 in a metal shed provided by EPNG.  It was still operating satisfactorily,
as of June 1972.  Two short down-times were experienced; one was due to
extreme cold  (<-20 F) and condensate freezing, and the other was due to a
plugged orifice which restricted the gas flow and altered the combustion
mixture.  To remedy the problem of freezing condensate, EPNG personnel
installed a small catalytic heater in the shed.  Data obtained by monitoring
non-contaminated gas from wells surrounding the Gasbuggy well indicated
concentrations less than the minimum detectable activity for the liquid
scintillation procedures at the Center.   This is exactly the result seen
from laboratory combustion of the pressure bottle samples.   The indication
is that the use of atmospheric oxygen for combustion presents no problems
in the way of sample contamination by atmospheric tritium.

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For the gas constituent assay combustion of one cubic meter  (STP)  of  gas
will produce 1200 ml of water; this combustion requires  approximately ten
cubic meters of air.  From air sampling experience in the area,  a  cubic
meter of air contains about three milliliters of water.   The comparison,
then, is that 30 ml of atmospheric water are aspirated for combustion as
opposed to more than 1200 ml of water produced by the gas combustion.
This is a dilution of only 2.5 percent.  Therefore, sample dilution by
atmospheric moisture is extremely small as compared to the large amounts
of water obtainable through combustion.  This is considered  to be  the
generally encountered condition in the western United States.  Calculations
based on high humidity conditions (97% RH @ 85°F) yield up to 30 ml of
water per cubic meter of air, giving a dilution up to 25%.  However,  this
does not reduce the usefulness of the burner for monitoring  purposes, but
does restrict its use for quantitative information.  Satisfactory  burner-
condenser operation was seen for an estimated temperature range of -20°F
through +140 F; however, no continuous observations were made of conden-
sation at these extremes.  Some doubt exists on the condenser effectiveness
above 130°F.

The second unit was constructed to be used at the Rulison site during the
third production test flaring operation.  The unit was to be used  to obtain
some experience on known contaminated gas and to get a comparison  of the
resultant data to that yielded by a pure Op oxidizer system  operated on-
site by Eberline Instrument Corporation (EIC).  The EIC oxidizer was a
commercially available sample oxidation unit for laboratory  use, modified
to give continuous gas combustion.  Subsequent sample procedures were
essentially the same as those employed by the NERC-LV for the burner
samples.  The EIC oxidizer was operated on the same gas line as the burner
and should yield comparable data.  The primary differences between the two
units are their oxidant supply and their adaptability to remote location
use.  The burner proved its usefulness for absolute measurement of tritium
in natural gas; a comparison of three sampling methods (Table 1, Table A-l)
supports this measurement.

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 Table 1.   Tritium Concentrations  in  Rulison Gas from Various Monitoring
           Methods.
NERC-LV Burner
pCi/1
5.0 x 104
1.2 x 104
1.5 x 103
EIC Oxidizer
PCi/1
5.0 x 104
1.1 x 104
3.3 x 103
Pressure Bottle-Lab Oxidation
PCi/1
5.0 x 104 5.2 x 104
1.1 x 104 1.2 x 104
1.0 x 103 3.6 x 103
A  continuous  comparison of the burner data and the EIC oxidizer data is
given  in Appendix A  (Figure A-l and Table A-l).  These results show that
the  burner  provides  good stability in the data and a very close comparison
to those data collected with an acceptable method.  The divergence of the
data toward the  later sampling dates is considered to be due to the
changing gas  composition (reduction of relative C0? volume), since all
the  data presented for the burner employ calculations based on the
February 10,  1971, gas composition assay.

                              CONCLUSION

The  described burner-condenser system provides an acceptable, reliable, and
inexpensive method to continuously monitor for radioactivity in natural gas
produced from wells  stimulated by underground nuclear explosives.  The sen-
sitivity of the  liquid scintillation methods employed by the NERC-LV provides
an analysis capability for tritium in the combustion water down to a minimum
detectable activity  of 400 pCi per liter of water.  This is equivalent to
500  pCi of tritium per cubic meter (STP) of natural gas having the same com-
position as that from the Rulison experimental well.  Operational experience
indicates reliable operation for estimated ambient temperatures ranging from
-20°F through +140°F, and data were obtained for natural gas known to have
background or elevated radioactivity levels.  Consistent and reliable sam-
pling has been shown by one of the units for a year-and-a-half at a remote
location near the Gasbuggy site.   Demonstrated applications of the system
include monitoring of normally uncontaminated natural gas for possible radio-
active contamination, and integrated sampling for quantitative determination
of tritium concentration in gas known or suspected to have elevated levels
of tritium.
                                   8

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For quantitative determination of the tritium concentration  in  natural
gas, it is necessary to have an accurate gas  composition  assay.   With
changing gas makeup, as encountered at Project Rulison, it is  necessary
to assay often enough to incorporate significant changes.   For  a  relatively
stable situation, as would be encountered on  a production  line, less fre-
quent assays are required.  However, if the intended use  is  to  monitor gas
for the possibility of contamination, no assay is required since  one is
looking only for data above the MDA to use as an action guideline.  More
accuracy would be desirable if positive results are seen.

Limitations on quantitative use of the burner system arise primarily from
two sources, (1) ambient air humidity, and (2) ambient air temperature.
The severity of the effect from these factors is determined  by  the  use for
which the system is intended.  Only attempts  to measure absolute  tritium
concentration will be hindered, while general monitoring  of  production
lines for radioactive contamination is unaffected.

The humidity problem mentioned previously can yield discrepancies in  the
data to as much as 25 percent by dilution.  This is resolved by periodic
measurement and subtraction of the contributed water volume during  data
reduction calculations.

The effect of ambient air temperature can be a complex interference.   The
condenser portion of the burner system depends on ambient air for coolant,
and condensation efficiency is therefore a function of ambient air tempera-
ture.  The problem arises when one considers the possibility of a signifi-
cant change of the tritium concentration in the natural  gas during a sampl-
ing period when the ambient air temperature may fluctuate widely.  No  simple
relationship will exist between the tritium concentration of the natural
gas and that of the combustion condensate water.  This is not considered
to be the normally encountered situation; however, should the possibility
exist the sampling time can be reduced so that the condensate tritium con-
centration more nearly reflects that in the gas being monitored.

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It is currently necessary to ship water samples (condensate)  to the Center
for analysis.  A project is underway at the NERC-LV to develop and test
an electronic tritium detection and printout system capable of remote and
independent operation.  This unit will automatically measure and record on-
site data on the tritium concentration in natural  gas at any given location,
and will relieve the question of ambient air temperature effect.
                                  10

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                              REFERENCES


1.  Johns, F. B. and Jaquish, R.  E., Gas Analysis Capabilities of the
    Southwestern Radiological Health Laboratory (SWRHL-91), April 1970.

2.  Johns, F. B., Southwestern Radiological  Health Laboratory Handbook of
    Radiochemlcal Methods (SWRHL-11), March  1970.

3.  Project Rulison - Final Operational Radioactivity Report - Production
    Tests (NVO-112). February 1970.

4.  Johns, F. B., Unpublished data.

5.  Standards for Radiation Protection, USAEC Manual Chapter 0524 (1968).

6.  Jones, W. M., Vapor Pressures of Tritium Oxide and Dueterium Oxide.
    Interpretation of the Isotope Effects, J.  Chem. Phys. 48:207-214 (1968)
                                  11

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                      APPENDIX A
Tritium Concentrations in Natural Gas - Project Rulison
                          12

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MAR 1 APR 1
SAMPLING DATE (1971)
               Figure A-l.  Tritium  in Natural Gas - Project Rulison


                                      13

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Table A-1.   Tritium In Natural Gas - Project Rulison
Sampling NERC-LV Burner
Period (x103pCi/l gas)
02/02
02/04
02/05
02/14
02/15
02/16
02/17
02/18
02/19
02/20
02/21
02/24
02/25
02/27
02/28
03/01
03/02
03/03
03/04
03/05
03/06
03/07
03/08
03/09
03/10
03/11
03/12
03/13
03/14
03/15
03/16
- 02/03
- 02/05
- 02/06
- 02/15
- 02/16
- 02/17
- 02/18
- 02/19
- 02/20
- 02/21
- 02/22
- 02/25.
- 02/26
- 02/28
- 03/01
- 03/02
- 03/03
- 03/04
- 03/05
- 03/06
- 03/07
- 03/08
- 03/09
- 03/10
- 03/11
- 03/12
- 03/13
- 03/14
- 03/15
- 03/16
- 03/17

84
78
55
52
50
46
41
43
40
40
34
32
32
28
27
24
26
24
23
22
22
21
21
20
18
16
15
15
15
15
,-x NERC-LV
EIC Oxidized ' Pressure Bottles
(x!03pCi/l gas) (x!03pCi/l gas)
97 98
83
80
57
52
50 50 52
51
43
44
35
40
28
30
33
25
25
25
25
24
22
20
20
19
19
17
18
16
15
14
14
13
                                  14

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Table A-l . Tritium in Natural Gas
Sampling
Period
03/17 -
03/18 -
03/19 -
03/20 -
03/21 -
03/22 -
03/23 -
03/24 -
03/25 -
03/26 -
03/27 -
03/28 -
03/29 -
03/30 -
03/31 -
04/01 -
04/02 -
04/03 -
04/04 -
04/05 -
04/06 -
04/07 -
04/08 -
04/09 -
04/10 -
04/11 -
04/12 -
04/13 -
04/14 -
04/15 -

03/18
03/19
03/20
03/21
03/22
03/23
03/24
03/25
03/26
03/27
03/28
03/29.
03/30
03/31
04/01
04/02
04/03
04/04
04/05
04/06
04/07
04/08
04/09
04/10
04/11
04/12
04/13
04/14
04/15
04/16
NERC-LV Burner
(xl03pCi/1 gas)
13
12
13
12
12
12
12
9.8
11
10
9.9
10
9.3
9.8
8.5
8.2
7.9
7.6
7.2
6.9
7.1
6.8
6.6
6.9
6.9
6.6
6.1
5.9
6.2
6.0
- Project Rulison (continued)
,.} NERC-LV
EIC Oxidized ' Pressure Bottles
(x!03pCi/l gas) (x!03pCi/l gas)
13
11 11 12
12
11
9.7
9.6
8.7
8.3
8.4
8.4
8.1
7.6
6.9
7.9
6.7
6.7
6.4
6.0
6.6
6.4
6.4
5.3
4.8
4.1
4.7
4.2
3.9
3.9
3.7
4.0
15

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Table A-l.  Tritium in Natural Gas - Project Rulison (continued)
                                                  ,-x         NERC-LV
Sampling         NERC-LV Burner       EIC Oxidized '      Pressure Bottles
Period	(x!03pCi/l gas)	(x!03pCi/l  gas)       (x!03pCi/l  gas)
04/16 - 04/17         6.1                    3.7
04/17 - 04/18         5.5                    3.5
04/18 - 04/19         2.9                    3.4
04/19 - 04/20         4.8                    3.3
04/20 - 04/21         4.1                    3.3
04/21 - 04/22         4.6                    3.2
04/22 - 04/23         4.3                    3.3
04/23 - END           1.5                    3.3              1.0       3.6
                                  16

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       APPENDIX B
Burner Component Drawings
           17

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T/A    ,
    ^DRILL AND TAP TO 1/4"x 28
ALL PARTS STAINLESS STEEL     |
                 Figure B-2.  Combustion Chamber
                               19

-------
VERTICAL
SECTION
COOLING t
   FIN
CUT ELL
AND BUTT WELD
                                                                           INTERNAL CONDENSING
                                                                           SURFACE
                                                                           ADDED TO
                                                                           VERTICAL
                                                                           SECTION
                    VERTICAL
                    SECTION
                   COOLING
                   FIN
                                               LEVEL LINE FORJ^DROP TODRAIN
                                               ' '                      (MIN.) \
      BURNER SUPPORT STRAPS
      MAKE 2 TO FIT. WELD TO ELL
                         PRIMARY CONDENSER- EXHAUST
                                                                                              C
                                                                                              33
                                                                                            (/) 03
                                                                              DRAIN IS 1/4"
                                                                              COPPER TUBE
                                                                              APPROX. 6" LONG
                                                                              WELDED AT
                                                                              CONDENSER
                                                                              LOW POINT
                                                                   SECTION A-A, SEE DWG. B-5
                             =* m
                               -
                               O
                               g
                               Tj
                               m
                               o
                  1V4" I.D. COPPER TUBE AND ELL
                  4" X 4" COPPER SHEET (RADIATOR PLATES)

-------
                         NATURAL GAS BURNER-MODIFIED
                                  VERSION #1
                                                      TACK WELD INTERNAL
                                                      SURFACE TO TUBE WALL
                                                      SECTION A-A,
                                                      SEE DWG B-6
PRIMARY CONDENSER
      SECTION       \^
                     \
                                        SECONDARY CONDENSER-EXHAUST
                                          1%" ID COPPER TUBE
                                          1" X 18" COPPER SHEET
                                          (RADIATOR PLATES)
                      Figure B-4.  Secondary Condenser

-------
                   NATURAL GAS BURNER-MODIFIED
                            VERSION #1
CROSS SECTION A-A OF DWG. B-3
PRIMARY CONDENSER
RADIATOR PLATE
                                FINS ARE .063 COPPER WITH 1% 0;
                                WELDED APPROX. 1/2" APART
                                ALONG 114" I-D.,M6"WALL COPPER TUBE.
                                           MAKE 24
             Figure B-5.  Primary Condenser  Radiator
                             22

-------
                 NATURAL GAS BURNER-MODIFIED
                           VERSION #1
CROSS SECTION A-A OF DWG B-4
SECONDARY CONDENSER
RADIATOR PLATES
                                    FINS ARE .063 COPPER 1" WIDE AND
                                    APPROX 18" LONG; WELDED TO 11/4" I.D.
                                    VJ6WALL COPPER TUBE.
                                                MAKES
                                    INTERNAL SURFACE PIECE .063
                                    COPPER APPROX 18" LONG, TO FIT I.D.
                                                MAKE1
               Figure B-6.
Secondary Condenser Radiator
     23

-------
                                   DISTRIBUTION

 1-15   National  Environmental  Research Center,  Las  Vegas, Nevada
     16   Mahlon E. Gates, Manager, NVOO/AEC,  Las  Vegas,  Nevada
     17   Robert H. Thalgott, NVOO/AEC,  Las  Vegas, Nevada
     18   Henry G.  Vermillion, NVOO/AEC,  Las Vegas, Nevada
     19   Chief, NOB/DNA, NVOO/AEC, Las  Vegas, Nevada
     20   Robert R. Loux, NVOO/AEC, Las  Vegas, Nevada
     21   R. M. Pastore, NVOO/AEC, Las Vegas,  Nevada
     22   Donald W. Hendricks, NVOO/AEC,  Las Vegas, Nevada
     23   Technical Library, NVOO/AEC, Las Vegas,  Nevada
     24   Mail  & Records, NVOO/AEC, Las  Vegas, Nevada
     25   Martin B. Biles, DOS, USAEC, Washington, D.  C.
     26   Director, DAT, USAEC, Washington,  D. C.
     27   Harold F. Mueller, ARL/NOAA, NVOO/AEC, Las Vegas,  Nevada
     28   Gilbert J. Ferber, ARL/NOAA, Silver  Spring,  Maryland
     29   Stanley M. Greenfield,  Assistant Administrator  for Research  & Monitoring,
          EPA,  Washington, D. C.
     30   William D. Rowe, Deputy Assistant  Administrator for Radiation Programs,
          EPA,  Rockville, Maryland
     31   Dr. William A. Mills, Dir.,  Div. of  Criteria &  Standards,  Office of
          Radiation Programs, EPA, Rockville,  Maryland
     32   Ernest D. Harward, Acting Director,  Division of Technology Assessment,
          Office of Radiation Programs,  EPA, Rockville, Maryland
     33   Bernd Kahn, Chief, Radiochemistry  &  Nuclear  Engineering,  NERC,  EPA,
          Cincinnati, Ohio
34 - 35   Charles L. Weaver, Director, Field Operations Division, Office  of
          Radiation Programs, EPA, Rockville,  Maryland
     36   Gordon Everett, Director, Office of  Technical Analysis, EPA,
          Washington, D. C.
     37   Kurt  L. Feldmann, Managing Editor, Radiation Data  & Reports, ORP,  EPA,
          Rockville, Maryland
     38   Regional  Administrator, EPA, Region  IX,  San  Francisco,  California
     39   Regional  Radiation Representative, EPA,  Region  IX, San  Francisco,  Calif.
     40   Eastern Environmental Radiation Laboratory,  EPA, Montgomery, Alabama
     41   Library,  EPA, Washington, D. C.
     42   William C. King, LLL, Mercury, Nevada
     43   James E.  Carothers, LLL, Livermore,  California

-------
     DISTRIBUTION (continued)

     44   Joseph Tinney, Hazards Control, LLL, Livermore,  California
     45   Charles I. Browne, LASL, Los Alamos, New Mexico
     46   Harry S. Jordan, LASL, Los Alamos, New Mexico
     47   Arden E. Bicker, REECo, Mercury, Nevada
     48   Savino W.  Cavender, REECo, Mercury, Nevada
     49   Carter D.  Broyles, Sandia Laboratories, Albuquerque,  New Mexico
     50   Robert H.  Wilson, University of Rochester, Rochester, New York
     51   Richard S. Davidson, Battelle Memorial  Institute,  Columbus, Ohio
     52   J. P. Corley, Battelle Memorial Institute, Richland,  Washington
     53   Frank E. Abbott, USAEC, Golden, Colorado
     54   John M.  Ward, President, Desert Research Institute, University of
          Nevada,  Reno, Nevada
     55   P. L. Randolph,  EPNG, El Paso, Texas
     56   G. W. Frank,  Austral Oil Co., Inc., Houston,  Texas
     57   G. R. Luetkehans, CER Geonuclear, Las Vegas,  Nevada
     58   A. E. Doles,  EIC, Santa Fe, New Mexico
59 - 60   Technical  Information Center, Oak Ridge, Tennessee (for  public
          availability).

-------