of
«anaqt-»eiit have teen :tevelor>e«1 to u point at which, if
vigor^nisli , wo»jlii result in risk to tie i>-b7i«- 'rubs-tdn
than thut fro* accidents to the reactor: .'M<-*i nrort«tc*;F'-'»~*CF; :.-:»?:.»; DISPOSAL;
GKK"»ftNY; 51*15*1 LR1TSIN; H\Z/H.K)UJ; 1 NTfcf'.SI TTO 1» 1 - » a^GVSrST ;
RADIO* CTIVE; tAFliTY; l»S
(14) FTERAhtl TEBKS: lhA/?PF; 11 • I*
(I1,) STIRS ACC.NO.: OCo'.i>2?l
(16) CITATION: 21 (.£17) : 16, AU rock formations, bait beds will
probably ce sites for early repositories. About i33.7 aillion will be
spent on terminal storage studies iiu 1977 to start a nine yr. progran.
Strong public opposition to studies or these i-ait formations karns of
trouble when disposal is planned. There are 50,000 sq . «i. of salt beds
in the U.S. in eaithquaxe free areas, and advantages over tne otner
geologic formations are noted. In assessing possible sites, tae area
tectonics, seismicity , erosion, structure, nydrogeoioyy , and aineral
resources will be analyzed. Tests will be done tor rock stress, heat
transfer, radiological etiects, and soix »ove»ent. 3'fco pilot plant
sites will be chosen by 1»7b. These will oe ejpunued to full scale
receiving rate and capacity in 1sl>0. oosts are unknown but sarety is
assured. In 1977, an enviioiinental impact stateaent oil waste management
will be published.
(12) K£V»ORDS: DISPOSAL; uEOLuulC; dAZA6DuUi;
SAFETY; SALX; SITfcS; US
(141 HIERABCK TERMS: iDii/^bn ; 1WA/2HF
(15) STIHb ACC.HO.: OOS42210
(16) CITATION: 5*9(1): id- tl , oac. 1977.
(1) SHIRS ACC.MO.:
(2) DOHESTIC: F (2) CAi'EGOtl: Oa (2) Suiid.TiPE: G
(3) ARTICLE TlTLi;: oraniua waste iesearcaers consider alternate
leans of tailing disposal.
(4) AUTHOR: Hoffett Li
(6) JOURNAL TITLE: Canaaiun Bininy Journal
(10) LABGOAGE: BH (10) GKO. AHjiA: 1CO (10) Pdli. J£AR: 1977
(11) ABSTRACT: Canada is the «orid*s secoud largest producer of
uranium, over 85 percent is produced cy the acid leaca process. The
industry disposes of about 11,000 tons of solid waste per day. Solid
waste may be disposed of oy land impoundment, lake disposal, or
backfill. The largest volume is impounded benind dams (typically about
500 acres with a 100 sdllion ton capacity) . Ail oi the solid wastes are
radioactive. Little can be done to attenuate the radiation from the
surface of the tailing area aud tne present practice is to restrict
access. There are presently over 1,00u acres of inactive tailing areas.
Rehabilitative efforts consist oi surtace treatment such as
establishment of a grass cover ana effluent control (effluent cones
from mine water, process waste, and surface drainage) . An analysis ot
typical final discharge effluents is givea together witu proposed
Federal regulations and guidelines tor the uranium industry. Major
contaminants are derived from chemicals added in the milling process
rather than from the ore. The recycling ot water is possible from mine
water, process rater, and final effluent. Tne protdea or liquid
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HAZARDOUS WASTE MANAGEMENT
effluents from surface drainage is almost exclusively associated with
inactive or abandoned tailing areas.
(12) KBIHOBDS: BASIN; CANADA; CttKHICAL; DISCHARGE; DISPOSAL;
DRAINAGE; EFFLUENT; HAZARDOUS; HYDRAULIC; LEACH; HIKE; RADIOACTIVE;
BECLAHATION; TAILINGS; WATER
(141 HIEBABCH TEBBS: 1DD/2DK; 1RA/2RG; 1SD/2SJ
(15) STIBS ACC.NO.: 00342182
(16) CITATION: 98(1):48-50, Jan. 1977.
(1) SBIHS ACC.NO.: 043071
(2> DOMESTIC: D (2) CATEGORY.: 09 (2) SUBJ.TXPE: T
(3) ARTICLE TITLE: Method and device for closing a receptacle for
radioactive wastes.
(4) AUTHOR: Beyer A
(S) CORPORATE AUTHOR: Groupement Activ. Atom, at Advan. "GAAA"
(7) PATENT DATA: O.S. Patent Ho. 4,016,096
tlOJ LANGUAGE: KB (10) GEO. AREA: 1EU/2FR (10) PUB. JEAR: 1977
(11) ABSTRACT: A method and a device for closing a receptacle for
radioactive wastes is described. The method of closing a barrel with an
inside lid and an outside lid separated by an 0 ring having two beads
is as follows: arranging the 0 ring on the top rim of the barrel, on
toe internal side, with the beads facing towards and away fro* the
interior of the barrel; resting the inside lid on the upper bead
bringing the 0 ring into contact with an annular *aste discharge port
external to the inside lid; orienting the barrel coaxially beneath the
waste discharge port for waste discharge; lifting the inside lid
axially fro* the Q ring and the annular ring and filling the barrel
with vaste; resting the inside lid again on the 0 ring upper bead;
driving the inside lid and the upper Dead downward toward the lower
bead below the level of the top ri» such that any surface portion of
the 0 ring seal between the beads subjected to possible radioactive
contamination during waste loading ot the barrel is blocked from
exposure to the barrel exterior; and installing the outside lid on the
barrel overlying the inside lid.
(12) KElfwORDS: APPARATUS; CONTAINER; HAZARDOUS; PATENT;
RADIOACTIVE; REFUSE
(14) HIEBARCH TERMS: ICI/^DV; IttA; 1RA/28H
(15) STIHS ACC.NO.: OOS42114
(16) CITATION: Le Plessis Robinson, France, filed Sept. 12, 1975
issued Apr. 5, 1977.
(1) SHIRS ACC.NO.: 042979
(2) DOBESTIC: F (2) CATEGORY: 09 (2) SUBJ.TYPE: S
(3) ARTICLE TITLE: The boviet answer to nuclear waste
(4) AUTHOR: Belitzky B
(6) JOURNAL TITLE: New Scientist
(10) LANGUAGE: EN (10) GKO. AREA: 1ED/2RU; 1US (10) POd. YEAR:
1977
(11) ABSTRACT: A fourfold expansion, planned by Soviet authorities,
for nuclear power has called for a drastic reappraisal of nuclear waste
disposal methods. Increasingly, boviet experts are guesioning the
storage techniques adopted by lestern countries. Although American
scientists clan a very low migration rate for radioisotopes from
storage of high level liquid and solid waste burial in crystalline rock
at depths of about 450 leters, studies By Soviet scientists have shown
unacceptable ligration rates. The disposal of low level and aediua
level fluid wastes has arranged in one area ot the DSSR in a porous
stratui consisting of quartz sandstone and clay. High level wastes lust
be solidified before ultimate disposal, generally by vitrification.
work is also underway to perfect such techniques as cenentation,
bituaunization, and fixation in ceramics or asphalt, cementation has
been employed for the disposal of low level wastes for a long tine.
(12) KEYWORDS: DISPOSAL; EUROPE; GEOLOGIC; HAZARDOUS; LIQUID;
POKEB; SAFETJ; SOLID; STORAGE; OS; UbSR
(14) UIERARCH TERHS: 1HA/2UF; 1UA/2HG; 1RA
(15) STIHS ACC.NO.: OOS42022
• 16) CITATION: 74(104B) :128-129, Apr. 21, 1977.
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RADIOACTIVE WASTES
(1) SBIRS ACC.MO-: 0*2961
(2) DOMESTIC: D (2) CATEGORI: 09 (2) SUBJ.TTPE: G
(3) ARTICLE TITLE: Fuel reprocessing and waste disposal.
(4) AUTHOR: Levenson B
(6) JODKHAL TITLE: Trans American Nuclear Society
(10) LANGUAGE: fcH (10) GEO. ABBA: UU; 1Ui> (10) POB. IEAH: 1977
(11) ABSTRACT: Unclear fuel reprocessing and waste disposal are
discussed. Standard reprocessing which separates uraniun, plutoniun,
and fission products into separate streans has i>een in operation over
30 years in 7 countries. Although «any countries are increasing their
nuclear programs as a consequence ot the oil crisis, no equivalent
increase in reprocessing capacity is underway. Reasons lor this
include: econo»ic and financial questions raised oy the instaniitiy of
the regulatory issues, safety, and national and international
uncertainty about proposed regulations. Public reaction to fuel
reprocessing and waste disposal, both in the U.S. and in Europe, is
examined. Issues raised by the public are noted and addressed. Current
concerns focus on hazards fro» man and nature: man in toe forn ot
terrorists and irresponsible countries; and nature in the fora of new
ice ages, new volcanoes, or instability in the currently accepted laws
of chemistry and physics. It is suggested that scientist*s aims should
be honest objective assessaent of the risks, open disclosure of
details, balancing of risks versus benefits, und recognition ot which
alternatives really exist and which alternatives and energy sources are
still only Hopes.
(12) RECORDS: bJLSPOSAL; ECONOMICS; KNE8G1; EUROPE; FUEL;
HAZABDOUS; INTERNATIONAL; REGULATIONS; SAFETX; US
(1U) HIEBAHCH TERHS: 1DH/2D.L; 1HA; 1Kb; 1KA
(15) STIHS ACC-NO.: OOS420G4 (15) SEU)NDARX AUTHORS: Ziiterero M
(16} CITATION: (25) :103-106, 1977.
(1) SBIBS ACC.MO.: 0«2910
(2) DOHESTIC: D (2) CATEGORY: 0* (2) SUbJ.TKPE: S
(3) ARTICLE TITLE: Preparation and characterization of sintered
giass-ceraaics froa calcined simulated high-level waste.
(4) AUTHOR: Sansel EG
(&) JOURNAL riTLE: nuclear technology
(10) LABGCAGE: EH (10) PUB. V£AK: 147?
(11) ABSTRACT: The developnent and characterizations of sintered
glass - ceraiics (SGCs) as a nonolithic waste torn for the ultiiate
storage of spent fuel fro» coomercial power plant radioactive waste is
reported. The SGCs developed iroi siiulat-«d conaercial fluidized bed
calcine provide an alternative waste tor» for ultnate storage.
Aluainosilicate flux, sintered kith calcine, inaobilizes and fixes the
waste within a glass - ceramic eatrix. High calcine concentration and
SSC densities caintaiu low waste volune, conserving on the number of
storage canisters required. SUC properties include hiyh resistance to
i«pact, thema1 shock and aqueous dissolution, which are desirable for
safe transport and storage. Porosxty in SkiC is useful in Binimizing
pressure buildup due to radioiytic gas generation and SGCs appear
suitable for storage with a centerline temperature as hiyn as BOO
degrees C. Low pressure Holding oi SGC into thin wall containers
appears practical as a aanufacturiny process.
(12) KEYWORDS: CEkAHIC; FLOlDJ^EiJ BED; FUEL; GLASi; PnOCEiS;
RADIOACTIVE;" RESIDUE; Sl'OfeAGE
(14) HIERARCH TERBS: 1HA/2HF; 15ft/2rC
(IS) STIHS ACC.NO.: OOS"*1»53 (15) SEuONUARy AUTBuhb: iserreth JB
(16) CITAT10S: 33(1) :b8-7b, Apr. 1977.
(1) SHIRS ACC.NO.: 042817
(2) DOMESTIC: P (2) CATHGOiU: U9 (2) SOBJ.flfPE: S
(3) ARTICLE TITLE: Can nuclear wastes be uuried at sea?
{1) AUTHOR: Griawood t
(6) JOURNAL TITLE: Hew Scientist
(10) LABGOAGE: EB (10) GiSO. ARtA: 1EU/2UK (10) Puts. J£AR: 1977
(11) ABSTRACT: A preliminary «sssess»ent of the raaiological
conseguences of nuclear waste disposal to the deep ocean floor Bade by
Great Britain's National Radiological Protection board is examined. The
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HAZARDOUS WASTE MANAGEMENT
report highlights areas where study sad information is required. Most
of the HkPB assessment was concerned witii developing ct model describing
how radioactive material deposited on the ocean floor coold eventually
lead to the irradiation 01 nan, especially through food chains.
Calculations show the douinant route o.t individual ana collective
exposure for three categories or nuclidt-s (based on time after disposal
at *oich they woud give rise to their maximum annual dose): short term,
less than 500 years; in termed tatt term, 500 to 10,00u years; and long
term, greater than 10,000 yeais. This dominant route would be fioji
eonsuaaing food derived from marine plankton. Seduction of short term
doses could be achieved by designing a container tor the wastes which
would last hundreds or thouiiands or years, only 0road conclusions can
be drawn froi the study. Bany siguiticant uncertainties need to ce
resolved 0efore the disposal of high level radioactive waste on the
ocean floor is acceptable.
(12) KEYWORDS; CON'I'AIMEK; DISPOSAL; i'UROft; G8£AT BRITAIN;
HAZARDOUS; MATHEMATICAL MOD EL; OCliAN ; jSADlA I'lON ; itAOIOACri Yt; KE3EARCH
(11) HIERAKCh TERHS: ICI/xDV ; 1.1A; lUA
(liij STIWS ACC.HO.: OUS41dbO (15) S£cO*iOARi AOl'MoBS: «ei.t> vJ
CITAI'ION: >J (104U! :70a-711. Mar. 2t,
(t> ShlKS ACC.NO.: 04/725
(2) BOHESTIC; F (2} CATBGOKI: Ot> (2) SUb,) ,1'IP i,; S; t
(3) ABTICLE rlTLE: Disposal of toxic wastes — II. i-oisonous and
radioactive wastes.
(4} AUTHOH; Hodcn PJ
(fc) JODBfiAL TJTLfi: conservation t, recycling
(10J LAHGOAGE: US (10) StO. ARtA: IhO/^UK (10) PUB. XEAK: 1976
(11J &BSTBACT: The dispusul ot poisonous and radioactive wastes is
exanined. For Bdny wastes, the toxicity cdnnoi. ce reduced and three
•ethods oi treatment are used; diupersai in rivers or the oceau;
storage on special protected sites; and reclamation, i'he source and
danger of radioactive wastes are discussed as are their occurrence,
measurement, and relative toicicity. Tfiere are two types of radioactive
wastes: low level activity and uigh level activity. In Great iiiitain,
disposal of low level radioactive waste is carried out by burying in
the ground in a remote area. Treatment of high level radioactive wastes
includes sealing it in specially shielded druas lor storage; this is
practiced with wastes from nuclear porfer station effluent cleaning
systems. Many countries are arranging disposal of radioactive wastes
with methods agreed by the In ternntional Atomic Energy Agency. Special
containers will De dcpositea in designated deep w«ter areas wnich will
gradually leak over a long period when the toxicity will have been
reduced. Hastes rroa chemical processing of nuclear fuel are presently
being stored as liguids in ^teel taflk_< unaer strict security at ttie
processing plants until researco detet mines how to dispose of them.
Proposed methods of disposal include eelting, underground disposal;
storage in frozen ice or rocks; or shootmg into the sun.
(12) KEYWORDS: BUKY; CHEMICAL; CG«U'AI»ER; ns^osAi.; JSUKUPC; ruEL;
GREAT BRITAIN; IN XEhNATlONA L; KEStAkCw; S'i-OKAGi,
(14J H1E«A6CB 1-ERH^: 1HA/^HI'; 1lD
(15) SflflS ACC.NO.: OOSU1/66
(16) CITATION: t ( 1) : 1 1a-l/fa, te'tb.
(1) SWIRa ACC.SO.: 0425t>d
(2) DOMESTIC: D (2) CA'rEuGJOt: Ui» (2) SUbJ .'i'lf it JS: S; T
(5) COKPOBATE AUTHOR: Panel on tana Burial
(6) aoOK TITLE: The Shallow rand aurial of Low-tfevtJ Radioactively
Contaeinated Solid wastes.
(10) LASGUAGE: EN (10) GKO. AKtA: 10.S/2CO; 1US//ID; 1US/2IL;
1US/2NM; 1US/20H; 10S/2SC; 1US/2TB; 1US/2i«A (10) PUe. YEAR: 1y76
(11) AbSTHACr: Results are i,iven oi a study uudertaxen by tne Panel
on Land Burial of the U.S. Atomic Energy commission to investigate the
conditions, practices, and problems involved in tne near surface ground
burial 01 solid waste con taminatea »ith low levelfc of radioactive
materials. Specific types oi coutamiooted materials dealt witc include
institutional wastes sucn as paper towels, iaooiatory gloves, aiiri even
construction materials from an obsolete nucleox re;actor. Summaries of
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RADIOACTIVE WASTES
sites surveyed and of other sites that play aii important role in this
sort, of solid waste generation/disposal are given, and include
mydrogeologic, climatic, physiographic, aod operational details ot
facility sites. Facilities visited were (1) the Los Alamos Scientific
Laboratory, Los Alamos, New Mexico; (2) the Rucky Flats facility in
Colorado; (3) the Hound Laboratory in ohxo; (4) the Argonne National
laboratory in Illinois; (5) the Idaho national Engineering Laboratory;
(6) the Ban ford Dorks facility in Washington; (7) tbe Oak. Kidge
National Laboratory in Tennessee; and (8) the Savannah River Plant in
South Carolina. The Panel concludes that present burial practices have
not created a hazardous situation, although data gathered on low level
radioactive contaminated wastes at oak Ridge ana Savannah facilities
positively identify waste leaching. (Ketained in SBIKS library)
(12) KEYWORDS: B08Y; COLOHADO; CONTAalNATE; DISPOSAL; FACILITY;
IDAHO; ILLINOIS; INVESTIGATION; LANil; LEACH; NEH MEXICO; OHIO;
OPERATIONS RBSEAkCH; RADIOACTIVE; REFUSE; SAFETY; SITES; SOOTH
CAROLINA; TENNESSEE; WASHINGTON
(14) HIEfiAHCH TERMS: tAE; 1HA/2BF; 1KA/2HU
(15) ST1HS ACC.HO.: OOS41611
(16) CITATION: Washington, DC, National Academy ot Sciences, 1976.
150 p.
(1) SHIRS ACC.NO.: 042337
(2) DOMESTIC: D (2) CATEGOBI: 09 (2) SJBJ.TYPE: S; T
(3) ARTICLE TITLE: Method for improving the incorporation of
radioactive wastes into a vitreous mass.
(4) AUTHOR: Bonniaud R
(5) CORPORATE AUTHOR: Commissariat a 1'Energie Atomique.
(7) PATENT DATA: U.S. Patent No. 4,009,990
(10) LANGUAGE: EM (10) FOB. YEAK: 1977
(11) ABSTRACT: A method for improving the incorporation of
radioactive wastes into a vitreous mass as well as a calcinator for
carrying out the method are described. The calcinating device is
provided with a rotatable drum, the axis of which is slightly inclined
with respect to the horizontal and is adapted to be mounted inside a
furnace where it is used for nixing and heating a mixture of sintered
glass particles and radioactive wastes. The calcinator has, at tbe
extremites, two flanges to which are fixed an upper sleeve on a level
with which open an inlet conduit for the radioactive liquid, a conduit
connected to a hopper for feeding sintered glass and a gas exhaust
conduit and a lower sleeve. The extension of the sleeve (which is away
from the drum) is provided with an opening for expelling the calcinate
obtained and transferring it to a smelting furnace. The calciuator is
also provided with a means tor rotating and sealing it. Since the bed
for treated substances moves, it serves to clean the calcinator,
rendering mechanical cleaning unnecessary.
(12) KEYWORDS: COMBINED; GASStS; GLASS; HAZAhDOOS; LIQUID; PATENT;
RADIOACTIVE; SOLID
HIERAKCH TERMS: 1DD/2IK); 1HA/2HG; 1PB; 1RA/2KG
STIBS ACC.NO.: OOS41J81 (15) SECONDARY AUTHORS: douan A;
PROCESS;
(14)
(15)
Sombret
CITATION: filed Pec. 27, 11.75 issued Mar. 1, 1977,
(1) SHIRS ACC.NO.: 042097
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUBJ.TYPE: T
(3) ARTICLE TITLE: Shroud for storing radioactive spent nuclear
fuel cells.
(4) AUTHOR: Hollou L
(5) CORPORATE AUTHOR: brooks and Perkins, inc
(7) PATENT DATA: U.S. Patent Ko. 4,006,3t>2
(10) LANGUAGE: Eli (10) P0t>. YEAR: 1977
(11) ABSTRACT: A generally tubular shroud for storing radioactive
spent nuclear fuel cells is described. Each 01 the tubular shrouds is
composed of inner and outer metallic tubes, preferably formed of
stainless steel, dimensioned to provide a space between the inner and
outer tubes. Tbe shroud is of rectangular cross section, as are each ot
the tubes, and tue four spaces provided at the sides of the shroud are
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HAZARDOUS WASTE MANAGEMENT
generally flat elongated spaces. Sandwiches formed of outer layers of
thin aluminum sheet and au intermedlate layer of boron carbide are
Inserted into the spaces. The sandwiches completely fill the spaces
with a suitable end overlap at the sides to prevent the escape of
neutrons. The shrouds in sposed vertically in the pool and the upper
and lower ends oi the spaces Between the tubes are suitably sealed by
folding over longitudinally i-rojectinc, end portions of one or both
tubes beyond the adjacent end oi the sandwich. The upper ends o£ the
shrouds have funnel constructions which include portions extending into
the upper ends of the spaces between tie tubes so as to provide an
effective seal.
(12) KEYWORDS: ALUMIHUB; CONTAINS; FUEL; HAZARDOUS; METAL; PATENT;
R1DIOACTIVE; STORAGE
(14) HISRA8CH TERMS: 1HA; 1RA/2HH; 1SH/2SO
(15) STIHS ACC.NO.; OOS41141 (15) SECOKDARY AUTHORS: Ball KR
(16) CITATION: iiled Nov. 17, 19/S issued Feb. 1, 1»77.
(1) SKIES ACC.iO.: 042071
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SOBJ.tYPE: S
(3) ARTICLE TITLE: Removal of rctdioactive contamination from a
nuclear reactor coolant.
(14) AUTHOR: Coo pec BH
(5) CORPORATE AUTHOR: Bestinghouse Electric Corp
(?) PATENT DATA: U.S. Patent Ho. 4,010,068
(10) LANGUAGE: EN (10) PUB. 1EAB: 1977
(11) ABSTRACT: The removal of radioactive contaminants fro* the
coolant of a liquid metal cooled fast breeder nuclear reactor is
described. The equipment consists of an oscillating cold trap system in
which one trap is loaded with reactancs while a second trap, in series
flow connection, is used to precipitate t-he radioactive contamination
and the excess reactants. When the reactants in the first trap are
exhausted, the direction of the flow is reversed; the heating and
cooling of the traps are also reversea. The second cold trap then acts
as the reactant supply, while the first cold trap operates to remove
the inpurities by precipitation. When the excess reactant has been
exhausted from the second trap, the How is again switched, reversing
the roles of the two cold traps. The system is continuously and
reversibly operated in this manner until the reactants can no longer be
used to precipitate radioactive contanination contained within the
reactor coolant. Sodium hydride, sodium oxide and sodium iodide may be
loaded into the oscillating cold trap system. They will effectively and
efficiently remove tritium, oarium 140, cesium 141, zirconium 95,
iodine 131 and iodine 125.
(12) KEYWORDS: COHTAKlM ATE; HAZARDOUS; PATEST; PRECIPITATE;
PROCESS; PUR1FICATIOH; RADIOACTIVE
(14) H1ERA8CH TERMS: 1HA; IRA; 1HA/2WD
(15) STIHS ACC.NO.: OOS41115
(16) CITATION: filed Bar. 3, 1975 issued Bar. 1, 1977.
(1) SHIRS ACC.NO.: 0420o3
(2) DOMESTIC: D (2) CATEGORY: C* (2) SUbJ-TYPE: S; T
(3) ARTICLE TITLE: Volume reduction oi spent radioactive ion
exchange resin.
(4) AUTHOR: Tiepel E«
(5) CORPORATE AOTHOfi: Westingbouse Electric Corporation
(7) PATENT DATA: U.S. Patent No. 4,00tt,171
(10) LANGUAGE: EN (10) PUB. YEAtt: 1977
(11) ABSTRACT: A process for reducing the volume of spent
radioactive ion exchange resius whicn have been used for conditioning
water circulated through a nuclear reactor is described. The spent
resins are discharged from the reactor system as radioactive wastes to
a spent resin storage tank in the form of a slurry. The slurry is first
vacuum dewatered to remove the tree water and then the intrinsic water
in the wet resin beads is reioveu by drying in a vacuum fiuidized bed
chamber utilizing superheated steam which also acts to fluidize the
bed. Further drying is accomplished by spraying the partially dried
resin and superheated steam through a steam injected two iluia nozzle
for further extraction of intrinsic water from the resins. The steam is
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1WHOACTTVE WASTES
discharged to a condenser and Uie dried resins to an evacuated disposal
drua. Approximate four to oj^e voiuae reductions from the resin/water
slurry to tne dried resin is abtaj.iidi>.ie £>/ practicing tae process. The
water removed from the wet resins ib condensed along with the
fiuidizing and transporting steam and sent oack to the reactor liquid
Haste processing system-
(12) KEYWORDS: CONCENTRATIOH; DhiiKG; FLUlDIZfiD *iU; hAiAKDOUb; IO1I
EXCHANGE; PATENT; RADIOACTIVE; jiEUUi-XIOIl; fifiblH; VOLUME
(14) filERARCB TERHS: 1HA; IRA; 1SK/2SM; Mb
(15) SUMS ACC.SO.: 0054110/ (1DJ SECONDARY AUTHORS: Kitzes AS;
Lee PK
(16) CITATION: tiled Se^t. 10, 1i*/3, issued Pea. 15, 1y77.
(1) SW1KS ACC.SO.: 0*42059
(2) DOMESTIC: D (2) CA'I£GOIy polyaerization dt temperatures froa 15 to 50 C. Tne
process may be carried out at noraal or elevated pressure. A vide
variety ot Bonovinyi compounds may fcu usea jjut styrene, vinyl toluene
and lethyl acrylate are preieired. A wide variety or ixiiyvinyl
conpounds lay be used but divinyi benzene and trivinyl Denzene are
preferred. Polyaerization catalysts wnicn react at roo« teaperature
sucn as azo-bis-isobutyronitrile are preferred although a nunuer of
different ones are available. The Hardening May take iron several hours
to 30 days and aay be hastened by heating.
(12) KEXHOBDS: KOKOPE; GBrtMANX; LIQUID; MATERIALS HANOL1NG;
OBGANIC; PATE8T; POLYflER; PHOC£iS; ^ADIOACTlVi; SAfJifl; STOttA<.E; XO/IC;
TfiAtiSPOBI
(14) HIERAflCH TE8HS: lHA/^H(i; 1^V2TC; ITF/iTH
(15) b'TIHS ACC.HO.: 00541103 (15j SECONt^Ahr AUTaOhS: orobniK S;
Hild <
(16) CITATION: tiled iiec- 20, l!>/4, issuea Fei>. 22, 1977.
(1> SK18S ACC.WO.: 04^040
(2) DOMESTIC: D {2} CATfctiOrfY : Oa (2) i>OBJ.XYPK: I
(3) AKXICLE 1'IPLE: ERDA's plans for auclear wastes rapped.
(6) JOURNAL TlfLis: Cheaical and Engineering News
(10) LANGUAGE: EH (10) PUB. fEAtt: 1J77
(11) ABSTRACT: The Eimrvjy Researcii and Development Administration's
(ERDA) plans for reburyin<3 uuclear wastes is criticized by «.ne National
Research Council's Panel on Laud flarial. The cibbk practice ot uurying
its solid wastes contaminated wita low levels of radioactivity in
snailOH urencnes and pits presents no threat to hunan health; but the
ERDA plan to exhune and reoury siuca 01 the wastes that were uurieu in
the earlier days of nuclear technology is considered hazardous. Tue
Panel recoanends disposal in a final repository. One of the Panel's
concerns the availability of smtacle curial land as the amount ot
waste increases with the construction of new plants and tae disaantling
ot present reactors and facilities as they become obsolete. The panel
outlines a number of principles tor tne selection ot future r>uriai
sites and recommends several safety measures.
(12) KEYWORDS: flORY; DISPOSAL; fLUSitkL.; HAZARDOUS; PACKAGING;
PROGRAM; RADIOACTIVE; WATERwAX
(14) fclERARCH TERMS: 1hA; lHi>; 1MA/2Hii; 1hA/2iiG
(15) STIHS ACC.NO.: 00341084
(16) CITATION: 55(3):7, Jan. 17, 1977.
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HAZARDOUS WASTE MANAGEMENT
(t) SKlhS ACC.KG.:
(2) DuHESTIC: D (2) CA'fUGOici: 0* {2} ^UisJ.riPiJ: a; T
(3) ABTiCLf I'l'fki: Radioactive wasts disposal or water containing
waste using urea-torBaluenyue resin,
(4) AUTHOR: Gabiin KA
(5) CORPORATE AUTHOR: Nuclear Engineering Company, inc.
(1) 1>1TE8T DA'j-A: U.S. Patent so. 4,U1G,1Gtt
(10) LANGUAGE: EH (10) PUB. XEA»: 1«77
(11) ABSTRACT: A nethod ot soiidiiyiny radioactive waste Material
containing free water ibto a tree staiidicg body using a area
formaldehyde resin is described. Tne radioactive waste *atenul if
concentrated to a level suitable ±or disposal. The water is contacted
witn ion exchange resin ueaas capable ot taxing up radioactive metal
cations and holding tue» within the resiii »at>s. The deionized water is
returned to a cooking loop una the wet resin beads containing the
radioactive components are disposed ot Ly encapsulating tnesi wituin a
bydrophilic resinous «atetiai. Any 01 tue usual urea f oradldeiiy de
coapositxons »ay oe used tor the nyarophiiic resin. The resin should be
capaole of curing to a nigh polyser u^on the addition oi an acidic
curing agent.. At ter tne waste oattria^ is iaaooilized vitnin a solid
Jsiocic ot oydrophilic resinous lateriax, it may ue waterproolea to
protect against leaching, ii atsireu. The waste idterial aay ue
concentrated either by evaporation OL nitration.
(t2) KEYMOBDS: LOhCKNTfi AI 10K ; CoNi'ROL; ION i.XCHAHGfc; LEACH; LIQUID;
PATENT; HADluACTI?E; EES1«; SOi-ID; taiaTE «ATti<; HATilK
(t4) HiERABCti 'fE«Hi>: 1HA; 1SA/2«G; IhA/^Kri
(15J ST1BS ACC.MO.; OOS4107i> (1f>J SfiCONijAtti ADTHOKS: iiausen LJ
(1b) (.ITAIlOJi : tiled Hov. 29, 1*7j issued Mar. t, 1977.
(t) SBIRS ACC.HO.: 041^16
(2) DOMESTIC: D (2) CATE^Ofcy: Cy (2) SUaJ .TX Pi; : :>; I
(3) ARTICLE TITLE: Shale as a repository lor radioactivt waste: tne
evidence from Oklo.
(4) AOTBOB: firookins Dti
(6) JOUHitAL TlTLfc: £nvironeentai Geology
(10) LAHGOAGE: EN (10) GEO. AhtA; 1AF/^GB (10) PUB. JEAK : 1976
(11) ABSTRACT: Study of the l.b billion year old uraniu* ore zones
at the Ofclo Mine in the Kepubiic o£ Gabon sho«s tnat many ot the
elements producea by fission nave been almost coupletely retained, as
evidenced J>y proper budgets ot stable daughter elements. Plutoniua,
rutheniun, the rare earth elenents, zirconium, and palladiua have been
effectively retained while most ctiaicopuile elements ejtniuit sose
degree of re«oDHizatioii. The uklo reactor orei., tj-gni_£ice«atly , occur
in shale infilled into a fracture systen in organo-ar ^ill<»ceoa£.
sandstone, bo many of the fission produced elements retained ii.i tnis
shale along with evidence tnat most others may nave ueeu oniy locally
redistributed lends support to considering unales iu geologically
stable areas for radioactive waste disposal.
(12) KE1(«iUBDS: AFRICA; DISPOSAL; fcAKTH; Lj&ACH; HlhK; fllNBhAL;
RADIOACTIVE; STOfaASE
(14) HIEHARCH TEKMS: 1HA; 1HA/2uG; IhA/^Bi,; 1Sn//i'u
(1i>) STlflS ACC.MO.: OOS409bO
(16) CITATION: 1 (5) :2S5-2b*«, 19/b.
(1) ShlRS ACC.NO-: 041852
(2) COHESTIC: D (2) CATiJCOKi; (>a (^) SUBJ.TXPE: G
(4) AUTHOR: HavKes N (10) GEU. AhtA: IEU/2GE (10) t'UB. DEAR:
1977
(11) ABSTRACT: The problen o± raaioactive waste generated by
nuclear plants in West Ueraany is discussed, kest Germany plans to have
35,000 Begawatts of nuclear capacity installed by 1985. A court .
decision is noted which stipulated that tne construction of a nuclear
plant in the country could not occur until a national policy for the
disposal of radioactive waste had been developed. Potential sites and
•ethods tor the disposal of radioactive waste are being considered by
governaent officials. The thick salt beds in the Lover Saxony area of
the country have lie en chosen as the only geological strata waich can be
276
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RADIOACTIVE WASTES
used for disposing of waste fro* nuclear reprocessing plants. Other
sites ace also being considered. Once a site has definitely been
selected, it Mill be used as a Haste management facility and as a
reprocessing plant. Opposition to the proposed dual facility is
significant.
(12) KEYWORDS: DISPOSAL; BOKOPB; GERMANY; PLANNING;
PLANT-INDUSTRIAL; POHKH; RADIOACTIVE; REGULATIONS; SALT; SITES
(14) HIEBARCB TERHS: 1DD/2D8; 1LB/2LD; 1KA
(15) SUMS ACC.NO.: 00540696
(18) DOC.CIT.: Uawkes, N. Science in Europe/nuclear wastes stymie
Best Germans. Science, 195(U2tJ2) :962-963, Mar. 11, 1977.
(1) SHIRS ICC.MO.: 041765
(2) DOMESTIC: D (2) CATEGORY: 04 (2) SOBJ.TYPE: S (10) GBO.
AHE1: IB* (10) PUB. YEAR: 1977
(11) ABSTRACT: the Energy Reseatca and Development Administration
(KRDA) is expanding its study of deep underground formations within the
United States to gather preliminary data on the suitability ot geologic
disposal for safe, terminal storage ot commercial nuclear wastes. Field
work, including core drilling, will be conducted along with geologic
literature studies. KRDA is preparing a draft generic environmental
impact statement on the commercial nuclear waste management program.
Bhen a particular location is selected as a potential waste repository,
an environmental impact statement specific to that location will be
drafted before EBDA submits a request to Congress for construction
funds. Public hearings will be conducted as appropriate. Geologic
formations to be studied and evaluated are itemized as are the steps
which will be taken to assess the repository potential of the
formations.
(12) KEYWORDS: DISPOSAL; GEOLOGIC; RADIOACTIVE; RESEARCH; SAFETY;
SUBS; STORAGE; UNDERGROUND
(14) UIERARCH TERMS: 1UA/2HG
(15) STIHS ACC.NO.: OOS40&09
(18) DOC.CIT.: £RDA proposes study of geologic formations for data
on underground sites for nuclear waste disposal. Professional Engineer,
47(1) :27, Jan. 1977.
(1) SHIRS ACC.NO.: 041620
(2) DOMESTIC: f (2) CATEGORY: 09 (2) SUBJ.IYPE: S; T
(4) AOTHOR: Dippel I (10) PUB. YEAR: 1976
(11) ABSTRACT: The decontamination of surfaces, as presently
practiced, generates large volumes of radioactive liquid wastes with
considerable loads of nonradioactive matter. Optimization work, aimed at
reducing the quantity of these wastes has been carried out on a liquid
cleaning agent, a washing agent lor contaminated protective clothing, a
decontamination paste, and decontamination with molten salts. The
pastes and molten salts, unlike other decontamination agents, can be
applied in thin layers, resulting in considertibly smaller amounts of
waste. These agents are therefore useful alternatives to liquid
decontamination media.
(12) KEYWORDS: COMPARISON; LIQUID; PURIFICATION; RADIOACTIVE;
REDUCTION; RESIDUE; SALT; TREATMENT; VOLUME
(14) H1ERARCH TERMS: 1RA
(IS) SUMS ACC.NO.: OOS40664 (15) SECONDARY AUTHORS: Hentschel D;
Kunze S
(18) DOC.CIT.: Dippel, T. , D. Hentscnel, and S. Kunze.
Dekontamination and dekontamiuationsaLfaelle. (Decontamination and
decontamination wastes. ) Kerntechnik, 13(12):526-531, Dec. 1976.
(1) SHIRS ACC.NO.: 041557
(2) DOMESTIC: D (2) CATEGORY.: 09 U) SDbJ.TYPB: S; T
(4) AUTHOR: ttebbington HP (10) GBO. AR£A: 1HA/2HG (10) PUB.
YEAR: 1976
(11) ABSTRACT: The need for an industry in the United States to
process spent nuclear fuels to remove fission products and plutonium,
and reclaim uranium, is discussed, in 19 years one private plant was
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HAZARDOUS WASTE MANAGEMENT
opened, and then shut dowu is. 1972, while another awaits a nuclear
Regulatory Commission license. The components and characteristics of
spent nuclear fuel are described. Fission products are the chief source
of heat and radiation ia spent fuel. Several months storage in uater
pools at the plant is the first step in treatment and research into
subsequent treatment done at Baniord, Washington, is outlined, the
processes irere successful and efficient and 9i> percent of the p.Lutonium
vas recovered; uranium was not recovered and there nas a large .mount
of waste. This Doric's value for the nuclear fuel processing industry
was the development of remote operation and maintenance, and
innovations of engineering design, and the plant used is described.
Soie of the components, properties, and problems of dealing witli spent
fuel and fission products are outlined, the chief fear ceing the
effects on public health.
(12J KEYWORDS: EUROPE; FUEL; GBBAT tsRITAlH; HEALTH; H1STOHY;
INDUSTRY; MAINTSMANCE; EADIOACTIVt; iiKCLArtAtlOS; SOLVKST; STORAGE;
TBEATBEHT
(14) HIERARCH TKRHb: tRA
(15) SUMS ACC.HO.: OOSaObOl
(18) DOC.CIT.: Bebcington, U. P. the reprocessing of nuclear fuels.
Scientific American, 235(6);30-41, Dec. 197b.
(1) SHIBS ACC.SO.: 0413b9
(2) DOMESTIC: T (2) CATEGORY: 09 (2) SUBJ.rifPE: T
(4) AUTHOR: Cave L (10) GEO. AKEA: 1MA/2MC; 1KA/2KG (10J PUB.
YEAR: 1976
(11) 1BSTBACT: Problems associated with the management and disposal
of nuclear waste are explored. It is pointed out that reprocessing and
vaste management is the nost urgent problem facing the nuclear
industry. The position of the inergj Kesearch and Developaent
Administration on nuclear waste is detailed. The administration"s
preferred choice of technology foi highly active waste is to convert it
from liquid to solid naterial within b years of its generation and then
dispose of evaporated solids in suitable geological formations.
England's policies on waste storage are described as well as France's
approach to the management of nuclear waste, international aspects of
waste management are examined. Consideration is given to the use of
concrete wells for storage, governmental responsibility and public
interest in the disposal of nuclear waste, commercial waste,
technological processes involved in the solidification of highly
actively liquid waste from fuel reprocessing, and the ultimate disposal
of active vaste. Tabular data are provided on tne characteristics ot
solidified high level waste.
(12) KE180BDS: DISPOSAL; EUBOPE; FRANCE; Ji'UKL; GREAT bRITAIII;
IHTER8ATIO8AL; LIQUID; SAMAGliftEBT; PfiOBLEHS; hADIOACTiVE; SITES; SOLID;
STORAGE
(14) HIERABCH TEBHS: 1R£/2fcH
(15) STIHS ACC.HO.; OOS40433
(18) DOC.CIT.: Cave, L. Hanagement of wastes iro« the LKR fuel
cycle. Nuclear Engineering international, 21 (250):6i-74, Nov. 1976.
(1) SHIRS ACC.HO.: 041373
(2) DOBEST1C: F (2) CA'i'EGOh*: Or* (e used to
convert exposure rate (mR/hr) into Ci (Curie) content in packaged or
drummed radioactive Waste. A model Dased on a cylindrical shape is
used. The conversion curves take into account changes in package
dimensions, waste density, and average gamma energy.
(12) KEYHOKDS: CONTAINER; DESIGN; MAIrfEHATiCAL MOUEL; MtASUi EHENTi,;
HOM1TOR; PACKAGING; RADIOACTIVh; SEEPAGE
(14) HIERARCB TEfcMi,: 1SA/2KH
(15) STIBS ACC.NO.: OOS40417 (15) SKCONDARK AUTHORS: Swindle HL
(18) DOC.CIT,: Bowman, h. B. , and D. L. Swindle. Determination of
the Ci content of packaged radioactive waste using measured dose rates.
Health Physics, 31 (5) :445-4t>0, «ov.
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RADIOACTIVE WASTES
(1) SHIRS ACC.no.: 041348
(2) DOMESTIC: F (2) CATEGORY: 09 (2) S06J.TYPE: S; T
(4) AUTHOR: Hamelle J (10) GEO. AREA: 1EO/2FR (10) PUB. XfcAR:
1976
(11) ABSTRACT: The interim storage and final disposal of nuclear
waste in France is examined. Provisions have oeen made for the storage
of high level liquid waste, and the construction of new storage tanks
is in progress. Factors limiting the disposal of nuclear waste are
noted, and data on the production of nuclear waste are provided. Safety
aspects of storage are detailed. The primary characteristics of storage
tanks for containment include tne following: (1) tanks are Made of
stainless steel with severe quality control requirements; (2) cooling
coils suspended inside the tanks are provided; (3) the primary cooling
circuit is a closed loop connecting plate exchangers to aerocondensers;
(4) agitation is performed by air pulsations; and (5) tank ventilation
is related to scrubbers. The French process of vitrification is
detailed. The suitability of geological fornations for the disposal of
nuclear waste is explored.
(12] KEYWORDS: OPPOSITION; DATA; DISPOSAL; EOROPJS; FRABCE;
GEOLOGIC; RADIOACTIYE; SAFETY; STORAGE; TANK
(14) HIEKARCH TEKHS: 1RA/2RG; 1R4/2RH
(15J STIHS ICC.BO.: OOS40392 (15) SECONDARY AUTHORS: Sousseiier Y
(18) DOC.C1T.: Ramelle, J. , and X. Sousseiier. Intern storage and
final disposal of nuclear wastes in Fiance. Kerntechnik,
18(12) :524-525, Dec. 1976.
(1) SHIRS ACC.RO.: 041331
(2) DOHESTIC: D (2) CATEGORY: 09 (2) SUBJ.TYPi!: S; T
(4) AUTHOR: Tatyrek AF (10) GEO. AKEA: 1BA/2HG (10) PUB. YEAR:
1976
(11) ABSTRACT: The formation and chemistry of pink waste water from
TUT processing are addressed. Based on experimental work and field
experience with TNT and pink water, it is shown that both are toxic
hazards. The treatment of pink waste water is classified according to
concentration and destruction Methods. Concentration methods include
distillation, reverse osmosis, carbon adsorption and regeneration,
polymeric adsorption and regeneration, foan separation, solvent
extraction, and water recycle. Destruction methods relate to
ozonolysis, ozonolysis and ultraviolet techniques, gamma radiation,
incineration, aqueous phase catalytic oxidation, and composting and
soil disposal. The effectiveness of these treatment methods is
detailed, and significant parameters of each treatment, method ace
noted. It is concluded that the major problem to tie overcome in tne
treatment of pink water effluent is the development ol an effective and
economic process for concentrating large quantities of the very dilute
effluent to a significantly more concentrated fora which may then be
readily destroyed. (Retained in SWIhS library)
(12) KEYWORDS: CONCENXBATiON; DISPOSAL; EXPLOSION; dAZARDoUS;
PLAHT-I1TDUSTRIAL; TOXIC; PRKATHilllT; HASTE HATEk
(14) H1ERARCH TEBHS: 1IC/2IY
(15) STIMS ACC.NO.: OOS40375
(18) DOC.CIT.: Tatyrek, A. F. Treatment of TUP munitions
wastewaters: the current state of the art. Dover, »J, Picatinny
Arsenal, Oct. 1976. 145 p.
(t) SHIRS ACC.MO.: 041116
(2) DOMESTIC: F (2) CATEGORY: 09 (2) SUBJ.TYPE: S; t
(4) ADTUOR: boden PJ (10) GEO. AKEA: 1HA/2HG (10} PUfc. YEAR:
1976
(11} ABSTRACT: The disposal of toxic and radioactive wastes is
discussed. Many industries use toxic chemicals, thus producing toxic
wastes some of which can be rendered harmless at the plant or reduced
by conversion to another fora. Treatment of wastes whose toxicity
cannot be reduced include dispersal in rivers or ocean, storage on
special sites, and reclamation. Mercury is particularly dangerous when
dispersed in water, as it concentrates in fish, with consequent danger
to consumers. Solid waste disposal is vainly ay placing the slurries
formed in settling ponds, and in Great Britain toxic chemical duaping
279
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HAZARDOUS WASTE MANAGEMENT
sites are licensed and radioactive wastes are handled by governmental
disposal service, The operation ol a licensed toxic waste dump is
described. The advantages and disadvantages of nuclear energy are
discussed and the occurrence and characteristics or radioactivity are
described, together with the different measurements of radioactivity,
and dosage effects. Comparative toxicity of lead, arsenic, and fission
products are presented, indicating that water dispersal is not possible
for radioactive wastes, and radioactive decay is very slow. The sources
of low, and high level activity radioactive wastes are given. In Great
Britain a 250 acre site is reserved for disposal of low level activity
wastes. Compression and baling of tne waste was found costly and added
another area of contamination. Incineration was costly and not us
effective. High level liquiu effluents are processed to remove solids
that can then be sealed in drums for transportation by rail to a
storage site.
(12) KEYWORDS: COMPACTION; KUKOJ>E; FISH; UREA! BK1TAIM;
IMCIHEBAtlOM; LICENSE; HERCURI; OCEAN; RADIOACTIVE; SITES; STORAGE;
TOXIC; TREATMENT; WATfcRBAY
(14) HIEBARCH TERMS: 1HA/2HP
(15) SUMS ACC.SO.: OOS40160
(1«) DOC.C1T.: Boden, P. J. Disposal of toxic wastes. 2. poisonous
and radioactive wastes. Conservation and Recycling, 1(1) :119-12B, 1976.
O) SHIRS iCC.HO.: 040973
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SObO.TXi-E: I
(H) AUTHOR: Herritt KF CIO) GEO. AKEA: 1LC; 1RA/2Rh (10) PUB.
IEAR: 1977
(11) ABSTRACT: The results fro* two test burials of high level
wastes, incorporated into nepheline syenite giass and buried in contact
with groundvater for IS yr, indicate that the nuclear wastes irom fuel
processing for a 30,000 MW(e) nuclear power industry could be
incorporated into such glass and stored beneath the water table in the
waste management area of Chalk River Nuclear Laboratories (C8HL)
without harm to the environment. The process was developed as an
alternative to solidification of spent fuel from nuclear power plants,
and in solution to the hazard potential of leaching, CRHL created a
material so durable that it could be buried underground without
containment. The material was a glass based on nepheline syenite, a
naturally occurring aluminosilicate mineral. Glass blocks were prepared
by combining a mixture of 85 percent nepheline syenite and 15 percent
lime with fission product solution in a ceramic crucible. The resulting
gel was dried, denitrated at 900 C (1173 fc) , and melted at 1350 C (1623
K) to form a glass. Volatile components, mainly ruthenium aiid cesium,
were adsorbed on a heated bed of fire brick and iron oxides. Two
further field leach tests are in progress.
(12) KEYWORDS: BORY; CANADA; COMMERCIAL; CONTAINER; EFFECT;
ENVIRONMENT; GLASS; GROOfcD HATEh; INVESTIGATION; LABORATORY; i-EACB;
RADIOACTIVE; SOLID; STORAGE; UNDERGROUND
(14J H1ERARCH TERMS: 1Gb
(15) STISS ACC.NO.: OOS40017
(1b) DOC.C1T.: Merritt, M. P. Higa level waste glass: field leach
test. Nuclear Technology, 3^(1}:bfa-9G, Jan. 1977.
(1) SBIRb ACC.NO.: 040971
(2) DOMESTIC: D (2) CATEGORY: Oy (2) SUfaJ.TYPE: S; T
(*t) AUTHOR: Hoore JG (10) GisO. AREA: 1LC; 1RA/2hH (10) PUb.
IBAR: 1977
(11) ABSTRACT: The rates at which strontium, cesium, plutonian, and
curium are leached rrom hydroiracture grout (a modiried cement) were
measured. These studies utilized the test method proposed by the
International Atomic fcnergy Agency or a modification that exposed
smaller specimens with a higher surrace to volume ratio to a larger
volume of leachant. In general, the isotope leach rate followed the
order: cesium, aoreso than strontium, more so taan curium, moreso than
Plutonium. The amount of an isotope leached as a lunction of time
depended on the composition of the ieachaiit and varied in the order:
distilled water, moreso than tap water, moreso than grout water.
Concentrating the waste by a luctor ot up to 4 (prior to incorporation
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RADIOACTIVE WASTES
into a grout) had little effect on the leach rate of either strontium
or cesium. A comparison of the leach data for the grout with results
reported previously by other investigators tor other products indicates
that the grout can provide leach rates comparable to those obtained for
wastes incorporated into borosilicate glass.
(12) KBYBORDS: ANALYSIS; COMPARISON; CONCRETE; GLASS; ISOTOPE;
LABORATORY; LEACH; MEASUREMENTS; RADIOACTIVE; SIMULATION; TIRE
(14) H1ERAHCH TERMS: 1A£
(15J STI8S ACC.HO.: OOS40015 (15) SECONDARY AUTHORS: Godbee HB;
Kibbey AH
(Iti) BOC.CIT.: Hoore, J. 6. , H. U. Godbee, and A. H. Kiobey. Leach
behavior of hydrofracture grout incorporating radioactive wastes.
Buclear Technology, 32(1):39-52, Jan. 1977.
(1) SHIBS ACC.NO.: 040970
(2) DOMESTIC: D (2) CATEGORY: 09 U\ SUbJ.TYPE: T
(4) AUTHOR: Colombo P (10) GEO. AREA: IDS/2111 (10) PUB- TEAR:
19T7
(11) ABSTRACT: Techniques are developed for the solidification of
radioactive wastes in concrete. Included are the sources, storage,
volume reduction, and solidification of liquid wastes at arookhaven
National Laboratory, Upton, New York., using the cement/vermicnlite
process, as well as solid waste treatment, shipping containers, and off
site shipments of solid wastes. The properties of low heat generating
high level wastes, simulating those in storage at the Savannah River
Plant, solidified in concrete were determined. Polymer impregnation was
found to further decrease the leachability and improve the durability
of these concrete waste forms. Hathematical models and numerous tables
are included.
(12) KEYWORDS: COATING; CONCRETE; CONTAIN KB; LEACH; LIQUID;
POLYMER; PROCESS; RADIOACTIVE; SOLID; STORAGE; TECHNOLOGY
(14) HIERARCH TERMS: 1MA/2MH; 1HA/2RG; 1RA/2RH
(15) STIHS ACC.NO.: OOS40014 (15) SECONDARY AUTHORS: Mielson RM
Jr
(18) OOC.CIT.: Colombo, P. , and it. fi. iielson. Jr. Some techniques
for the solidification of radioactive wastes in concrete. Nuclear
Technology, 32(1):30-38, Jan. 1977.
(1) SilRS ACC.HO.: 040969
(2) DOMESTIC: D (2) CATEGORY; Ob* U) SOBJ.TYPE: T
(4) AUTHOR: Mickland CE (10) GEO. AREA: 10S/2CO/3RF (10) PUB.
YEAR: 1977
(11) ABSTRACT: Large quantities or plutoniun contaminated waste are
generated at the U. S. Energy Research and Development Administration's
(ERDA) nuclear weapons facility, the Rocky Flats Plant. Liquid and
solid wastes are generated and treated to produce immobile, stable,
solidified wastes. Effective waste aanageaent techniques have been
incorporated to significantly reduce the volume of waste. Pacxaging
systems have been designed to meet the 20 yr retrievability
requirement. The sources of waste generation and the treatment
processes performed at Rocky Flats as well as the waste packaging
systems utilized to meet U. S. Department of Transportation and ERDA
requirements are discussed.
(12) KEYWORDS: COLORADO; CONTAINER; CONTAMINATE; CRITERIA; DESIGN;
FACILITY; FEDERAL; MANAGEMENT; OPERATIONS RESfcARCh; RADIOACTIVE;
REDUCTION; RESIDUE; STABILIZATION; VOLUME
(14) HIERAKCH TERMS: 1PM; 1KA/2kb; 1SM/2TC
(15) STIHS ACC.HO.: OOS40013
(18) DOC.CIT.: uickiand, C. &, Packaging *ocky Flats waste. Nuclear
Technology, 32(1):25-29, Jan. 1977.
(1) SHIRS ACC.HO.: 040968
(2) DOMESTIC: D (2) CATEGORY: 0* (2) SUBJ.fYPE: S; T
(4) AUTHOR: tterreth JR (10) GEO. AREA: 1SM/2SO (10) POb. YEAR:
1977
(11) ABSTRACT: Corrosion measurements on stainless steel Dins used
to store high level waste (HLK) calcines at the Idaho Caeiical
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HAZARDOUS WASTE MANAGEMENT
Processing Plant indicate an internal corrosion rate of 0. 13 •• over
500 yr- From a corrosion standpoint, the existing bins or canisters
stored in air will last more than 500 jr. Synthetic commercial HLHs
solidified by fluidized bed calcination have been stabilized (nitrates
and water removed) at 620 to 720 C to periit their storage in sealed
canisters. Heat transfer properties in the canister storage ot the
basic HLB forms were calculated, based on specified canister
configurations, cooling Media, and maximum permissible product or
canister wall temperature, for a 150 HTO/yr commercial reprocessing
plant. The number of canisters required annually varies from
approximately 150 to bOO canisters/yr. Numerous tables are given.
(12) KEYBORDS: CHEHICAL; COBTAIHER; CORROSION; FACILITY; FLOIDIZED
BKD; HEAT; IDAHO; HEASOREMEUTS; HETAL; PROCESS; PROJECTION;
HADIOACT1VE; SOLID; STABILIZATION STORAGE; TiHE
(14) HIERAECH TERHS: 1BA/2RH
(15) STIHS ACC.NO.: OOS40012 (15) SBCOHDARX AUTHORS: Hoskins AP;
Hindileisch JA
(18) DOC.CIT.: Berreth, 0. R. , A. P. Hoskins, and J. A.
Bindfleisch. stabilization and storage of solidified high-level
radioactive wastes. Nuclear Technology, 32(1)i16-24, Jan. 1977.
(1} SHIRS ACC.BO.: 040967
(2) DOHESTIC: 0 (2) CATEGORY: 09 (2) SUBJ.TYPE: T
(4) AUTHOR: Mershad EA (10) GEO. AK£A: 10S/20U (10) PUB. YEAR:
1977
(11) ABSTRACT: Operations conducted at Hound Laboratory (Boiasanto
Research Corporation), Hiamis0urg, Ohio include the routine handling of
•ultigram quantities of tritium in various research, development, and
analytical systems. These operations produce radioactively contaminated
effluents that must be processed to remove tritium, tritium oxide, and
tritiated pump oil vapors before release of tne effluent gases to the
environment. In the process ot decontaminating the effluent gas stream,
appreciable quantities of tritium contaminated liquid wastes are
collected. Because of increased emphasis on minimizing tritium release
to the environment, considerable effort has been expended in areas of
containment, safe handling, aud disposal of tritiated liquid waste.
Mound Laboratory has developed facilities and methods for the safe
handling and packaging of this liquid waste. The primary objectives of
all tritiated waste packaging procedures are to (1) minimize effluent
releases and personnel exposure during packaging; (2) ensure integrity
of the primary containment; (3) minimize tritium permeation to the
secondary and tertiary containment; (4) prevent or minimize isotopic
exchange with groundvaters; (5) comply with 0. s. Energy Research and
Development Administration snipping regulations for radioactive wastes;
and (6) meet U.S. Department of Transportation shipping requirements.
(12) KEYWORDS: BUHY; CONTAINER; COHTAHISATE; EFFLUENT; FACILITY.;
LABORATORY; OHIO; OIL; OPERATIONS RESEARCH; RADIOACTIVE; TECHNOLOGY;
TREATMENT; HASTE NATEtt
(14) HIERARCH TERMS: 1RA/2RH; 1SM/2SO; 1SH/2TC
(15) STIHS ACC.NO.: OOSU0011 (15) SECONDAH 1 AUTHORS: Dauby JJ;
Thomasson H«
(18) DOC.CIT.: nershad, £. A. , H. U. Thoaasson, and J. J. JJauby.
Packaging of tritium-contaminated liquid waste. Nuclear Technology,
32(1):53-59, Jan. 1977.
(1) SHIRS ACC.NO.: 040966
(2) DOHESTIC: D (2) CATEGORY: 09 (2) SOBJ.TYPE: T
(4) AUTHOR: Jackson RR (10) 6EO. AREA: 1US/2WA/3HN (10) PUB.
YEAR: 1977
(11) ABSTRACT: The strontium (,Sr) and cesium (Cs) fractions
separated from high radiation level wastes at Hanford are converted to
the solid strontium fluoride and cesium chloride salts, doubly
encapsulated, and stored underwater in the Haste Encapsulation and
Storage Facility. A capsule contains approximately 70,000 curies (Ci)
(2. 59 PBq recommended maximum package) of Cs137 or 70,000 to 140,000
Ci (2. 59) to 5. 18 PBq) of Sr90. Materials for fabrication of process
equipment and capsules must withstand a combination of corrosive
chemicals, high radiation dosages, and, frequently, elevated
282
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RADIOACTIVE WASTES
temperatures. rue two metals selected tor capsules, Hasteiloy C-276 for
strontium fluoride and Type 316i stainless steel for cesium chloride,
are adequate for prolonged containaent. Additional aaterials studies
are being done Both for licensing strontium fluoride as source material
and for second generation process equipment -
(12) KtYiORDS: CHLQiUiiS; CGNTAlfcKh; CORfcObluN ; CRiTjsiilA ; FACILITY;
MABAGEMfiHT; METAL; OPKfiiTlOKS fi£S£AhCH; PttOCKSS; RADIOACTIVE; SALT-
SBPABATING; STABILIZATION; STuRAGK; KiShlftGXON ; WATEfi
(1«) HIERABCH TEKHS: IRS/^Sb; 1i«/VSCN ; ISM/^Tu
115) STIHS ACC.NO.: OOS40010
(1b) bOC.CIT.: Jackson, fi. JK. Kaniord waste encapsulation:
strontium and cesium. Nuclear technology , 32 (1) : 10-15, Jan. 1977.
(1) S«IRS ACC.MO.: 040965
(2) DOMESTIC: D (2) CATKiiOKY : 09 U) SUbJ.TYPE: T
(4) AUTHOR: Eister KK (10} £OB. iTEAR: 1977
(llj ABSTRACT: Radioactive trastes generated in the coemercial
nuclear power program are to i»e converted to a staitle package fora and
sent either to a Federallj operated repository or to coamercially
operated shallow land burial sites. The status of alternate
technologies to perform tnese operations has recently ceen reviewed and
published. American and Canadian »c±teriais research aud development
activities related to the co»»eicia.i package nastes cover a wide range
of waste forins and related waste trratnent tecnuologies for the various
types of radioactive wastes. At this ciae, specific projects are under
way and scheduled for conpletion to provide tne plant scale technology
required for the engineered facilities for was.te «.anageaent. Sources,
characteristics, and treatmtnt aethods of the waste generated are
discussed, as well as storage projections a-nd criteria for long tera
•anageaent .
(12) KEYM08DS: fcOfiSf; COHM fchCUAL ; DISPOSAL; £Nt,IN£KKl«IG; PKCILITI;
FBDEBAL; HANAGEM JSMT; fROCiSi.; KADlOACrlVJi; SK5KA8CH; SITES;
STABILIZATIOB; STOHAGK; TbChBOLOGK ; TRANSPORT; OSUEfiGfiOON D
(14) HZEhAfiCB 'i-EKBb: 1»V^^H
(15) STIHS ACC.NO.: OOS40009
(18) 00C.CIT-: Eister, H- K. Haterials considerations in
radioactive waste storage. Nuclear Technology, 32(1):6-», J«in. 1977.
(1) SHIRS ACC.UO.:
(2) DOBESTIC: D (2) CATEGORY: 09 (2) SUbJ.rYfE: G
(4) AOTH08: ftochlin Gl { 10} GEO. AitEA: 1SB/2TD (10) POo. JtiiAR :
1977
(11) ABSTRACT: Technical irreversibility and site aultiplicity are
suggested as criteria for safe nuclear waste disposal. In the absence
of goals or comprehensive regulatory otandards on nuclear waste
disposal, three types of waste treatment are generally employed: (1)
short ter« disposal; (2) long ter» storage; and (J) disposal. Tecanical
irreversibility and site multiplicity are recomaended for use in
organizing nuclear waste manageient options in teras of insuring
continued isolation from the biosphere in the face of Doth social and
geological uncertainties. Haste products resulting from (the nuclear
fuel cycle are discussed, and criteria tor sate waste disposal methods
are examined. Tecnnical irreversioiii ty is defined as the degree to
wnich emplaced waste is resistant to recovery or release, eitner oy
accident or by the deliberate application of technology. Technical
irreversiuility measures resistance to both social and physical
intervention. Tabular data are provided wnich classify several waste
disposal methods according to tneir uegree oi technical
irreversibility. site multiplicity is considered to aid in ainimizing
the adverse effects o± conceptual oi design errors in tiie disposal of
nuclear waste. The application of technical irreversibility and site
multiplicity criteria to nuclear haste Management is discussed.
(12) KEYMOKDS: CRiPBHiA; bESiGN; DISPOSAL; PUBLIC; KADIOACT1VE;
BESIDOE; SAFETY; SITES; STORAGE; J'£ChSiOLO(,Y
(14) HIEfcAHCh TERMS: 1RA/2hG
(15) STIHS ACC.SO.: OGS3iia^
(1ti) DOC.CIT-: Rochlin, G. i. Nuclear waste disposal: two social
criteria. Science, 195 (4273) : 23-31, Jan. /, 1977.
283
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HAZARDOUS WASTE MANAGEMENT
(1) SHIRS ACC.HO.: 040942
(2) DOBESTIC: D (2) CATEGORY: 09 ( PUB. YEAR: 1977
(11) ABSTRACT: The proposal oi the Energy Research and Development
Administration tor the storage of high energy radioactive waste in
stable geologic locutions is reported. The proposed plan has received
the endorsement of the Nuclear Regulatory Commission's independent
advisory committee on reactor safeguards. Noting that the first one or
two storage sites will retain the option to retrieve waste if anything
goes wrong, toe advisory committee feels that the Nuclear Regulatory
Commission should establish appropriate criteria for licensing and
regulating such facilities. The committee stressed the need for a
better understanding of the long term risks associated with the
disposal of high level radioactive Haste. Potential health problems
associated with the proposed storage plan, according to the advisory
committee, are primarily of a chronic low level nature and will
decrease substantially during the first few hundred years of decay. It
is recommended that, in tne development of criteria for disposal
facility licensing, the Nuclear Regulatory Commission include a
definition of the forms of Haste acceptable for storage and required
conditions of waste durability and integrity through some stated
minimum period. Consideration should also be yiven to the volume of
waste that may have to be retrieved and actions to t>e taken following
such retrieval, including contingency plans for waste storage. Toe need
for continued research on the long tern transport or transuranic
elements in geologic structures and on the uptake and retention of
radionuclides by plants and animals is emphasized.
(12) KBISORDS: ADMINISTRATION; CKiTERiA; DISPOSAL; ENtRGJ; .FEDERAL;
GEOLOGIC; HAZARDOUS; RADIOACTIVE; SAFtTI; STORAGE
(t4) HIERARCH TEKHS: IMA
(15) STIHS ACC.NO.: OOS3998fa
(18} DOC.CIT.: Nuclear waste disposal plan gets NRC okay. Cbemical
and Engineering Dews, 55(2) :6, Jan. 10, 1977.
(1) SHIRS ACC.VO.: 0407B9
12) COHESTIC: D (2) CATEGORY: 09 (2) SOBJ.TXPE: T
(4) AUTHOR: Straub CP (10) GEO. AREA: 18A (1U) PUB. HEAR: 197b
(11) ABSTRACT: Literature pertaining to radioactive wastes is
reviewed. The U. S. Energy Research and Development Administration
lists 2, 140 references on radioactive wastes. Hearings before tiie joint
Committee on Atomic Energy summarized information on the status and
directions for handling waste materials generated by tbe nucleac power
industry to the year 2000. Treatment aspects of radioactive wastes are
dealt with as are a patented method for the adsorption or chemisorptiou
of radioactive ions, and transmutation of the long lived hazardous
radionuclides strontium 90 and cesium 137. Storage of radioactive
wastes was the subject of two investigations. The National Academy of
Sciences report reviewed three concepts for interim storage of
solidified high level radioactive wastes. Twelve articles consider the
topic of fixation. Comparative data on the various parameters affecting
radioactive waste solidification as a guide to plant designers and
operators is presented. Investigators found tue Aeroject VR 20
Radioactive Haste Management System of fluid bed calcination more
economical than conventional solidification processes. Ground disposal
of radioactive wastes was the subject of three articles while ocean
disposal was discussed in nine. Edmonson et dl have prepared a
bibliography of 570 non Russian references on marine radioecology while
a bibliography oy Lehmann contains 1->1 abstracts on ocean disposal of
wastewater, sludge, dredge daaterial, disposal of radioactive wastes,
brines, and industrial wastes, forty four articles and publications are
reviewed.
(12) KEYWORDS: BI&LiOGRAPUX; DISPOSAL; £M£RGX; FKDEBAL; HAZARDOUS;
ISOTOPE; LITERATURE; OCBAN; RADIOACTIVE; STORAGE; TREATMENT
(14) HIERARCH TERMS: 1DD/2DW
(15) STIMS ACC.HO.: OOS39t»33
(IB) DOC.CIT.: Straub, C, P. Industrial wastes: radioactive wastes.
Journal Hater Pollution Control federation, 4t» (6) :1305-131 1, June 197&.
284
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RADIOACTIVE WASTES
(1) SUBS ICC.«0.: 040763
(2) DOflESTIC: P (2) CATEGORY: 09 (2) SUBJ.TYPE: S; T
(4) AUTHOR: Smith Cf (10) GEO. ABEA: 1HA/2RU (10) PUB. TEAR:
1976
(11) ABSTRACT: One of the major concerns with the continued growth
of the nuclear power industry is the production of the high level
radioactive wastes which are by products of the fission process. The
risks associated with the disposal of high level wastes derive from the
potential for release of radioactive materials into the environment.
The assessment of these risks requires a methodology tor risk analysis,
an identification of the radioactive sources, and a method by which to
express the relative hazard of the various radionuclides that comprise
the high level waste. The development of a methodology for risk
analysis is carried out after a review of previous work in the area of
probabilistic risk assessment. The methodology suggested involves the
probabilistic analysis of a general accident consequence distribution.
In this analysis, the frequency aspect of the distribution is treated
separately from the normalized probability function. In the final stage
of the analysis, the frequency and probability characteristics of the
distribution are recombined to provide an estimate of the risk. The
characterization of the radioactive source term is accomplished using
the ORIGEI computer code.
(12) KEYWORDS: ACCIDENT; ANALYSIS; BOKY; COMPUTER; DISPOSAL; FUEL;
GENERATION; HAZARDOUS; ISOTOPE; MANAGEMENT; MATHEMATICAL MODEL; POHEfi;
RADIOACTIVE; TECBJiOLOGT
(14) BIERARCH TEHHS: UE
(IS) STIBS ACC.NO.: OOS39827 (15) SECONDARY AOTHOhS: Kastenberg
UK
(18) DOC.CIT.: Smith, C. P. , and If. B. Kastenberg. On risk
assessment of high level radioactive waste disposal. Nuclear
Engineering and Design, 39(2-3}:293-333, Nov. /Dec. 1976.
(1) SwIBS ACC.NO.: 040758
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUBJ.TYPE: T
(4) AUTHOR: De Bacci M (10) tOb. YEAH: 1976
(11) ABSTRACT: A method of preparing liquid waste fission products
for storage is described. The method of preparation IB as follows: the
waste fission product particles are overcoated by tumbling them with a
powder mixture which includes alpha silicon carbide, carbon and a
carbonaceous thermosetting binder while a solvent is applied to make
the binder tacky; the overcoated particles are consolidated at a
temperature to thermoset the binder and form a green body; the bodies
are reaction sintered by heating, initially at a temperature to
carbonize the binder, then at a temperature to melt the silicon carbide
enclosing the waste fission products. The temperature for melting the
silicon is about 1600 C.
(12) KBXwORDS: CARBON; COATING; LIQUID; PATENT; PitOCESS;
BADIOACTIVE; SILICON; SIHTEfi; STORAGE; THERMAL
(14) HIEBABCH TEKHS: 1BA/2KH
(15) SUMS ACC.NO.: OOS39B02 (15) SECONDARY AUTHORS: frice MS
(18) DOC.CIT.: De Bacci, H. , and M. s. Price. (United Kingdom
Atomic Energy Authority, London). Preparation for storage of fission
products. U. S. Patent No. 3,994,b22; filed Jan. 29, 1975; issued Nov.
30, 1976.
(1) SHIRS ACC.NO.: 040600
(2) DOMESTIC: P (2) CATEGORY: 09 (2) SUBJ.TYPE: T
(4) AUTHOR: Bonniaud b (10) SEO. AREA: 1EO/2PE (10) POB. YEAR:
1976
(11) ABSTRACT: Continuous vitrilication of nigh level radioactive
wastes in Prance taken to the industrial plant scale is discussed. The
first prototype equipment for continuous vitrification was operated for
8000 hr with various simulated fission product solutions. A second
prototype has been built particularly to demonstrate remote nandling
operations. Current developments are directed to the following areas of
importance: a study of the continuous vitrification or fission product
solutions from the reprocessing of PBR; the examination of the
feasibility of continuous denitration prior to vitrification and the
285
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HAZARDOUS WASTE MANAGEMENT
effect ot this treatment upon the operation ot the caiciner; increasing
the throughput of the caiciner by increasing the How rate and
continuously concentrating prior to calcination; furnace capacity; the
effect of high heat to the centerlines of the furnace blocks; and the
effects of thermal shocks occuring in the glass during external
decontamination of the container. Plant operation conditions are
described.
(12) KBIHOROS: E0ROPE; FKAUCB; FUKMACE; GLASS; faEAf; OPERATIONS
RESEARCH; PLAHT-IBDUSTHIAL; PROCESS; RADIOACTIVE; SAFETY
(14) HIERABCH TEkBS; 1RA/2BS
(15) STIHS ACC.BO.: OOS39644
(18) DOC.CIT-: Bonniaud, H. Continuous vitrification in France
takes to industrial plant scale. Nuclear Engineering international,
21(250) :67-69, MOV. 1876.
(1) S«IRS ACC.MO.: 04057«
(2) DOHESTIC: D (2) CAT3S60KX: 0» (2) SOBJ.TIPE: T
(4) AUTHOR: Bucnell LR (10) GEu. AREA: lKA/2Kt; (10) PUB.. YEAR:
1976
(11) ABSTRACT: High level radioactive wastes are encapsulated in
vitreous carbon for longter* storage. The wastes are mixed as finely
divided solids vith a suitable resin, foraed into an appropriate shape
and cured. The cured resin is carbonized l»y heating under a vacuu* to
for* vitreous carbon. The vitreous carbon shapes, aay i*e further
protected for storage by encaseaeat in a canister containing a low
•elting temperature matrix oaterial sues as alumiuusi to increase inpact
resistance and improve heat dissipation.
(12) KEYHORDS: DISPOSAL; UA2.AfcDOUi>; METAL; NON-FKKROUS; PATENT;
PROCESS; RADIOACTIVE; RESIH; STORAGE; TR^ATMEHT
(It) H1ERAHCB TE8HS: 1SH/2TC
(IS) STIBS ACC.NO.: OOS39622 (15) SBCONUAKY AUTHORS: bates JL
(18) DOC.CIT.: Bunnell, L. h. , and J. L. Bates. Bethod ot
encapsulating solid radioactive waste aaterial foe storage. U. S.
Patent Mo. 3,993,579; filed Oct. 22, 1*75; issued Nov. 23, 1976.
(1) SHIRS ACC.HO,: 040601
(2) DOHESTIC: F (2) CATEGORY: oi» (2j SUBJ.TXPE: s
t<») AUTHOK: Corbet A (10) GEO. ABEA: 1EO/2FK; t£D/2DK (1 image:
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RADIOACTIVE WASTES
has been analyzed in this study. The changes, occuring during the
thermal treatment with glassy materials, i. e. drying, transformation
processes, sintering, melting, etc. , have been followed using
emanation (radon) tnernal analysis (t-fA) . The method of ETA gives
information useful in the evaluation of a suitable fixation system and
process. The combination of eifects ot sintering, reaction product gas
release, and related phenomena, can 0e studied. The "closing" and
"opening* of the solid state structure is of considerable importance in
optimizing the process of solidification of highly active nuclear
wastes. Six figures and a table illustrate the rq>ort.
(12) KETBORDS: ANALIS1S; DISl'OSAL; HAiJVKDOUS; RAIUUACTIUE;
BBSEARCH; SINTER; SOLID; THERMAL
(14) HIEfiABCH TEEMS: 1RA/2RG
(15) ST1MS ACC.HO.: OGS39445 (15) SECONDARY AUTHORS: Kouriffl V;
Plasil F
(18) DOC.CIT.: vojtecn, 0. , f. Plasil, and V. Sourim. The use of
emanation thermal analysis lor the investigation of radioactive waste
fixation processes. Journal of Rddioaualytical Chemistry, 30:583-592,
1976.
(1) SSIHS ACC.SO.: 040386
(2) DOMESTIC: F (2) CATEGOHI; 04 U) SOBJ.I7.PE: S
(4) AUTHOR: Lewis Jti (10) G£O. AREA: 1EO/2UK (tO) PQtt. IEAR:
1976
(11) ABSTRACT: the problems ot treating and disposing ol small
a Mounts of radioactive wastes from nuclear power projects are
discussed. The major source of radioactive Hastes is the mel element
reprocessing plant. Here the fuel is decauned and dissolved in nitric
acid so that the uranium can fie recovered and, together with the
Plutonium that has been formed, separated froi the fission products.
High, nedium, and low activity efflueuts are produced and each stream
•ust be treated appropriately. Alternative systems for disposal and
storage of liquids and solids are described and the relative direct and
total waste management costs of each are estimated. Nuclear
transmutation and various longrange problems relative to particular
types of radioactive wates are discussed.
(12) KEXBORDS: DISPOSAL; KNVIROIiWKNT; EXPOSURE; FUEL; GASSES; G8EAT
BRITAIN; HAZARDOUS; ISOTOPE; i.igUID; PARTICIPATE HATTER; PROBLEMS;
RADIATION; KADIOACT1VE; SOLID; STORAGE; WASTE MATER
(14) HIERARCH TERMS: 1KA/2Rt>
(15) STIHS ACC.NO-: OOS39430
(18) DOC.CIT.: Lewis, J. B. Kadioactive wastes and nuclear power:
methods of treatment. Physics in Technology, 7(2):77-b4, Bar. 1976.
(1) SilRS ACC.NO.: 0403B5
(2) DOMESTIC: D (.2) CATEUORX: 09 (2) SUBJ.TIPE: S
(4) AOTHOB: Cohen BJ. (10) PUb. ItAB: 1976
(11) ABSTRACT: 1-he potential hazards of the high level waste
produced in one year froa all nuclear fuel reprocessing plants in the
United States are calculated os a function of time lor direct gamma
radiation, inhalation, and ingestion, and scales are given ror
consequences of tne worst credible handling, the probability tor Buried
waste to be released into the environaent by i»everal pathways is
estimated, and several factors ot related interest are discussed. It is
concluded that" the potential hazards in these wastes are not
inordinately large in conparison with those of other hazardous
materials used in our society, such ay arsenic, bariua, copper,
chlorine, ammonia, hytirogen cyanide, etc. The requirement for caeap,
abundant energy is stressed. Four figures and two taules accompany the
report.
(12) KEYWORDS: AHBONIA; CHLORINE; EFFtCT; EtfVlRONfliiBT; GEOLOGIC;
GBOOND SATEh; HAZARDOUS; HEALTH; ^ON; ION EXCHASGE; IbOPOPE; LEACH;
PARTICOL1TE MATTER; RADIATION; RAD10ACT1KK; UNDERGROUND
(14) BIERARCH TERMS: 1RA/2RG
(15) STIMS ACC.NO.: OOS39429
(18) DOC.CIT.: Cohen, B. L. Environmental impacts ot high level
radioactive waste disposal. IEEE Transactions on Nuclear Science,
23{1J:56-59, Feb. 1976.
287
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HAZARDOUS WASTE MANAGEMENT
(IX SHIRS ACC.WO.: 039862
(2) DOMESTIC: P (2) CAii'uoRY: 09 (2) SUfcj.TYPE: s n<>) PUB.
YEAB: 1976
(11) ABSTRACT: The vacuum freeze distillation method was
successfully applied to the preparation ot radiocneaiically pure water
saaples used for deteraining the tritiua concentration in highly
radioactive liquid waste produced in nuclear iuel reprocessing. This
•ethod yielded a decontamination factor exceeding 1 aillion for
radiorutheniun and other long lived fission products. The isotope
effect on the tritium concentration was corrected by applying an
enrichment factor deterained iroa ex^eriacnt. A snail portion of the
high level liquid waste solution was taken from the Reprocessing Plant
of tne Japan Atomic Energy Research institute, neutralised *ith 2
noraal sodiua hydroxide,, and subjected to tae vacuua freeze
distillation. The distillate was subsequently analyzed tor tritiua by
liquid scintillation counting, the tritiun concentration in the waste
solution was found to be ctpproxiaaely 0. 13 aicrocuries per ailliliters
which corresponded to about 70 percent of the total tritiua contained
in the original spent fuel rods.
(12) KtlHORDS: CHEMICAL; COSCJSNTftA'ilON; DISTILLATION; EFFECT;
FREfcZIHG; i)APAN; MEASUREMENTS; PROCESS; RADIOACTIVE; hESEARCH; VACOOfl;
WATER
STIMS ACC.NO.: OOS3890t>
i/OC.CIT.: Tachimori, S. Determination of tritiua concentration
in fuel reprocessing liquid waste by vacuum freeze distillation.
Journal of Nuclear Science and Technology, 13 (6) :442-««4a, Aug. 197b.
(1) SHIES ACC.NO.: 0397*1
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUoJ.TYPE: X (10) PUB.
YBAtt: 1976
(11) ABSTRACT: flethods ana apparatus for disposing of radioactive
waste liquids by solidifying the liouids into hardened lasses suitable
for disposal by burying are described. Disposal of at least partially
radioactive waste aateriai is accoaplished by intermixing the waste
with a liquid containing a jelling agent consisting of an aqueous
suspension of partially polyaerized urea foraaldehyde and a curing
agent to fora a free standing Hardened Bass. The operator ot the
apparatus can without exposure to the adaixed aass of waste accurately
determine when the Bass is rully soiiditied. The aixture is then placed
in a container, monitored for the appropriate tiae to add a curing
agent alter which the aixture is retained until hardening is coaplele
and a surface free of waste water is achieved. The container and its
solidified aixture Bay then ce curied tor disposal. The waste Material
includes reactor evaporator bottoas.
(12J KEIHORDS: BUM; COATIKG; DISPOSAL; HAZARDOUS; LIQUIi); PATENT;
POLYMER; RADIOACTIVE; SOLID
(15) bTIBS ACC.NO.: OOS38835
(1b) DOC.CIf.: Gaulin, K. (Kuclear Engineering Loapany, Inc. ).
Methods of disposing of radioactive waste. U. S. Patent No. 3,<»db,977,
filed Feb. 3, 19/b; issued Oct. 1», 1976.
(1) SBIRS ACC.NO.: 039703
(2) DOMESTIC: F (2) CATEGORY: 09 (2) SUbJ .ntti: 3 (10) PUB.
YKAR: 1976
(11) ABSTRACT: The chances of radioactive wastes iroa nuci€!cir power
stations being ingested uy j.eopie and caut-ing cancer deaths ar€! put
into perspective with detailed nuneiicai. estimates. Tne parameters of
the study are defined togetner with tne metnou used to neasure dosages.
A graph displays the ingestion Hazard. A coaparison aa aade between tne
potency of arsenic and the careless way it is handled and the care that
is taken with radioactive waste. An idea that has received much
attention is incorporating the haste icto pyrex glass. Geographical
location of disposal sites has received much attention as has tne
possiuility ot leaching by groundwater. Human intrusion could also
occur, aainly tiirouya drilling the tait in wnich wastes have oeen
buried. The unlikelihood uf botn tnese occurences is explained.. The
probability of cancer deaths is calculated anu. displayed in a
283
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RADIOACTIVE WASTES
supporting graph. Care would be needed initially, for about 600 years,
in Hatching waste repositories, but the burden is small and distant
progeny would be more likely to regret present squandering of
hydrocarbons than to notice the tiny increase in radioactivity in their
environment.
(12) KEJiORDS: DISEASE; DISPOSAL; ENVIRONMENT; GEOGRAPHIC GLASS;
GROUND WATER; HAZARDOUS; HEALTH; HYDROCARBON; LJiACH; POiiEB;
HADIOACTIVE; SALT; TOXIC
(15) SUBS JICC.HO.: OOS38747
(IS) DOC.CIT.: Cohen, B. L. Storing radioactive wastes need not be
a problem. Nuclear Engineering international, 21(2U*):3a-41, Oct. 1976.
(1) SHIRS ACC.NO.: 039675
(2) DOMESTIC: t (2) CATEGORIC 09 (2) SUBJ.TYPE: G (10) PUB.
SEAR: 1976
(11) ABSTRACT: Computerization ot the radioactive ship»ent records
(RSR) system for the Haxey Flats low level nuclear waste burial site
near Borehead, Kentucky is discussed. In 1972, the Kentucky
Radiological health Department initiated a project to transfer the
information contained on RSR onto magnetic computer tape. Data
transferred daring the project comprised nearly 200,000 computer cards
containing information on the burial period from 19b3 to 1972. Each of
•the records on the computer tape contained up to /5 pieces of
information. Information items used for determining tne Haxey flats
inventory were the burial data, buriai location, isotope buried,
activity of the buried isotope, volume of waste material burned, and
sometimes a footnote number for messages that could not be included in
the record. The correction of mistakes in computer records is
described, and the waste inventory of the site, as provided in records,
is calculated. The inventory is examined according to several
classifications: activity for the site and burial pits, accumulated
activity by isotope, and waste volume. Comparisons are made with other
methods of inventory accounting. It is shown that existing records are
not completely reliable. Possible reasons for mismatching are
postulated,
(12) KfilMOflOS: BUfiX; CLASSIFICATION; COMPUTER; DATA; KENTUCKY;
MONITOR; RADIOACTIVE; SITES; TRANSPORT
(15) STIBS ACC.NO.: OOS38659
(18) DOC.CIT.: Gat, U. , J. D. Thomas, and D. T. Clark. Radioactive
waste inventory at the Maxey Flats nuclear waste burial site. Health
Physics, 30 (3) :2ai-269, ttar. 1976.
(1) SHIRS ACC.NO.: 0394S8
(2) DOMESTIC: D (2) CATEGOKJ: 0* (2) SUbJ.TYVE: S; T (10) FOB.
IEAR: 1976
(11) ABSTRACT: A patented process for toe safe disposal, handling,
and storage of radioactive waste is detailed. The invention relates to
the disposal of radioactive waste associated with nuciear power
production processes. It is shown that the addition of alkali or
alkaline earth silicate to radioactive waste cementing material mixture
produces a number of advantages over other radioactive waste disposal
processes. These include direct solidification of all common nuclear
power industry radioactive waste, including boric acid solutions; rapid
hardening to a gel in less than 2 minutes, eliminating requirements for
continuous mixing to insure homogeneity; solidirication oi maximum
hardness in less than 7 days, coaparea to 26 days for cement alone
without the alkali silicate additive; increased water retention over
nonsilicated processes due to the higo capacity of silicates tor water
fixation by hydration; production of more fluid mixes, causing ready
adaptability to batch or continuous processing of radioactive waste;
and minimum operator training and control required to obtain solidiiied
283
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HAZARDOUS WASTE MANAGEMENT
waste in a form suitable tor safe handling and shipment. Procedures
used in the invention for processing radioactive waste are detailed.
(12) KEYBOBDS: ALKALINE; BATCH; CONCRETE; CONTINUOUS; DISPOSAL;
£ARTH; PATEII; PROCESS; RADIOACTIVE; SAFETI; SILICON; SOLID; STORAGE;
TREAT (IE NT
(15) STIflS ACC.NO.: OOS38502
(18) DOC.CIT.: Curtiss, D. H. , and H. w, Heacocfc. (United Suclear
Industries, Inc. ). Radwaste disposal by incorporation in Matrix. U. S.
Patent No. 3,988,258; filed Jan. 17, 1975; issued Oct. 26, 1976.
(1) SHIRS ACC.ItO.: 039421
(2) DOHESTIC: F (2) CATEGORY: 09 (2) SUBJ.TXPE: T (10) PUB.
xBABl 1976
(11) ABSTRACT: A report is presented on the international symposium
on management of radioactive wastes fro* the nuclear fuel cycle (March
1976, Vienna, Austria). The symposium was sponsored by the
International Atomic Energy Agency and the Nuclear Energy Agency of
OfcCD (Organization of European Community Development). A major topic of
interest at the symposium was technology for the reduction and
incorporation of high level radioactive liquid waste, containing
essentially all of the radionuclides produced from the use of nuclear
power, into solid forms for safe interim storage and eventual disposal.
These solid products were characterized and evaluated as to their
suitability and long term stability. Presentations also indicated that
•any countries now are examining the possibilities of disposing of the
solidified, high level waste products and the longer life plutonium
(alpha) contaminated waste into suitable geological formations. Papers
abstracted in this report covered the following topics: and planning,
removal of gaseous radionuclides, treatment of low level waste,
treatment of hulls and solvent, solidication of high level waste,
evaluation of solidified high level waste products, conditioning medium
level waste, management of alpha bearing waste, geologic disposal, sea
disposal, and radioactive waste burial.
(12) KEYHORDS: AUSTRIA; 6BRY; CONFERENCE; DISPOSAL; EtfEKGX;
GEOLOGIC; INTERNATIONAL; MANAGEMENT; OCEAN; PLANNING; RADIOACTIVE;
STORAGE; TREATMENT
(15) STIHS ACC.NO.: OOS38465
(18) DOC.CIT.: Lennemann, H. Management of radioactive nast«;S from
the nuclear fuel cycle, report on the International Symposium held in
Vienna from March 22 to 26, 1976. Atomic Energy Review, 14 (2):421-429,
June 1976.
(1) SUIRS ACC.NO.: 039417
(2) DOHESTIC: f (2) CATEGORY: 09 (2) SUBJ.TTPB: S (10) PUB.
YEAR: 1976
(11) ABSTRACT: bacteria of the genus fhiobacillus and Ferrobacillus
have been discovered in leachate from numerous ore mines. The effect of
these bacteria on the leaching of waste uranium materials from which 70
to bO percent of uranium was previously removed by classical chemical
hydrometallurgical procedure has been investigated. The bacteria, used
are found in the ore and the mine water of ZletovsJca River locality,
Jugoslavia. Parameters of bilogical leaching were examined in tue
laboratory. Conditions were changed Mith the aim of increasing the
amount of uranium leached. The effect or pyrite added to the waste
materials before the beginning of leaching has also been studied.
Uranium leaching is directly proportional to the composition and number
of ferrobacteria and thiobacteria, and increased by almost twice the
value obtained from the same starting materials without using bacteria.
(12) KEYWORDS: BACTERIA; CHEMICAL; EUROPE; HAZARDOUS; LEACH;
MICROORGANISM; MINE; RADIOACTIVE; YUGOSLAVIA
(15) STIflS ACC.NO.: OOS38461
(18) UOC.CIT.: Barbie, F. F. , D. M. jiracilovic and fi. ¥.
Kajincanic. Bacterial leaching ot waste uranium materials. Zeitschrift
fuer Allgeneine HiXrobiologie, 16 (3):179-186, 1976.
290
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RADIOACTIVE WASTES
(1) SW.IRS ACC.tfO.: 030970
(2) DOMESTIC: D (2) CAT£^OfaS: u» (2) SUhJ.Titi: S; r (10) PUb .
YBAKi 1975
(11) ABSTRACT: The magnitude and uatuie of the radioactive waste
proolem are discussed. Kadioactive waste is a necessary bypioduct
associated with the deration oi nuclear reactors. Nuclear reactors are
operated for the production oi electric energy, propuo.sj.ou ot snips,
production o£ nuclear weapons ana otner special nuclear Materials, and
research and; testing. Many types oi radioactive waste originate as
solutions, so»etises very dilute, ana tney all contain saterials otner
than radioactive isotopes tneasej.vei>. « hile «ost laoiuactivt. waste is
at one tiae in the torn ot solutions or diurri.es, it is a steadily
increasing trend and in sone cases a legal requirement to convert sucu
waste to a solid fora. The overall management or radioactive waste is
reviewed, with esnpftasis on tur» soj.iUiiicat.ion and storage or disposal
of solidified waste. Consideration is given to fi&siou and activation
proaucts, fissionable material, con tan nation, nuclear tuei reprocessing
and types of waste generated, interi* storage ol liquid waste,
solidification aria treatment of iuw Itvel waste, solidification of ttigh
level waste, storage of solidifieu radioactive waste. Federal
repository for high level waste, and future i aprovemeiits in t.ie
disposal ot radioactive waste.
(12) KEYWORDS: bY-PROvUCI'; MANAfiKthHI; KADIOACTlVr); SfOtsAbE
(tb) STlflS ACC.Nu.; OOSjyOlt
(18) DOC.Cir.: Buocnam, J. A. aanugement of radioactive wastes. In
tlanteil, C. L. , ed. jolia hastes; origin, Collection, Processing, and
Disposal. New rorK, John mley aj.d iions, Iy75. p.
(1} SMIRS ACC.MO.:
12) 0UWESTIC: F U) CATKUOHY: Oj (2) SUtiJ-IYPK: T I1C>) PUB.
1*76
(11) A&ST8ACT: hadioactive wastes irora nuclear power plants is
stored in rock slat toriationt sale tioa ieacaate. A new disposal
system designed uy Steag-Kej.n energie company is described based on the
conditioning and soliuification 01 radioactive wastes in mobile units
operating at tne nucieai power luciiity. I'he couditioitine consists of
treatment that prevents leaching. A picture or tht "Faua* mobile unit
for conditioning rauioactivt Bastes is given. It was put in operation
in Novenoer 197S. It weighs 20 tons aud may l>e aoved by a tiucK. During
3 aiontha the unit processed aad solidified bu cubic meters oi mediuai
active resins froa Gunareaniiingeu nucj.ear power plant aim transported
then to tie salt nines of Asse. (Text in uerman)
(tij KEXxOKDS: CONTROL; U^iiFOiiAL; E^UiPMEMT; ^ikHANK; LKACS;
MUVABLE; PROCESS; RADIOACTIVE
(IS) STlfiS ACC.HO.: uOS37b?0
(1b) JOC.CII1.: iiaatz, H. aehaudluny von raiiiOak tiven ablaellen aus
KernKraf twerken tuer die Eriuidgei ung. (Treatiiiy radiouctive waste from
nuclear power plants for teisunal disposal- ) Atoa untt
22 (4) :103-104, July/Aug. 1^V(>.
(1) SHlRS ACC.SO.:
(2) DOMESTIC: P i2) CA J'EbOftY : uy U) SUfcJ.J'Kfi,: T (10) PUB.
TEAK: 1976
(11) ABSTRACT: The researcft and Uevtlopjient projects 101
reprocessing of nuclear power wastes, at tne ivdrxsruce society ror
Nuclear Kesearca are evaiuatea, especially irom tne Viewpoint of
safety. The designing stage concern^, itself with the construction and
future operation of a large scale reprocessing plant tor water reactor
fuel. The planning stage is ai> ~;ood a*, coiopieted, out tneie are still
• any gaps in the safety aojiaiu, ci>ptcially in tue training of personnel
that would have tue necessary experience to uuiid and run a large scale
reprocessing plant foi nuclear wastes, tor a 1,500 ton per year plant,
there would oe over 50,000 cubic meters or waste yielding (upon
29.1
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HAZARDOUS WASTE MANAGEMENT
reprocessing, concentration ana soliuification) a^ove 4,uUO cubic
•eters of disposable Haste, (text in German)
(12) KBYBORDS: DESIGN; DISPOSAL; GBBSANi; PLASNISu;
PLANT-I»DOSTR1AL; POUEB; HAuIOACXlWtl; B£SLAfiCu; SAFEtY
(li) STlJlS ACC.NO.: OOS37627
(18) DOC.C1T.: Koch, G. flat den keg zur sicheren wieueraufbereitung
(Towards a safe reprocessing ot nuclear wastes, j
Atomwirtschaf t-Atoatechuik, 21 (6) :314-3 ID, Juiie 197o.
it) SWIRS ACC.MO.: 036716
(2) DOMESTIC: D (2) CAl'EliOhl: 09 U) SUBJ.TYtE: S; 1' (10) PUo.
1976
(11} ABSTRACT: A aetaod for recovering cesium (Cs} and palladium
(Pd] values from nuclear reactor lission product waste is described.
The aethod requires no pH atQustmeiit ana permits nitric aciu recycle.
Under oxidizing conditions, Cs and Pd are recovered from nitric acid
fission product solution as an insoiui/le precipitate after contact with
a chloriae source. 1'he source can be a soluble cnloride or other
coipound which yields chloride ions in solution. The precipitate is
predominantly a combination ot Cs, F-a and chlorine. The oxidizing step
is carried out electrolytically. After recovering the precipitate,
Cs2PdClb, contacting of the fission product waste solution with a
source of nonradioactive Cs ions to cause the precipitation ot
additional Cs2PdCl6 and the recovery of tne additional precipitate is
detailed.
(12) KEYWORDS: CHLOKIUE; OXIDATION; PATENT; PhfcCli-li'ATE;
BADZOACTITE; SEPARATlttG
(15) S'i'lHS ACC.NO.: OOS37/60
(18) DOC.CIT.: Campbell, i>. (U. S. iinergy Hesearca and Development
Adainistration). Recovery of cesium and palladium fro* nuclear reactor
fuel processing waste. U. S. Patent No, 3,979(49o; riled Aug. 6,
issued Sept. 7, 1976.
(1) S¥1HS ACC.MO.: 03B672
(2) DOBESTIC: D (2) CAI'EGORX: 09 (/) SUBJ.TIPE: X (10) PUB.
YEAR: 1976
(11) ABSTRACT: Delegates to the International Sy«posiu» on the
Hdnagement of Hastes £ro» the LWK (li^ht water reactor) Fuel Cycle
(Denver, July 1976) discussed the procleaa of radioactive waste
disposal and the need for international standards. United States Energy
Research and Development Administration director H. C. seamens said
that LHB offers tne only plausible route towards energy independence.
In Europe, a 15 country association (.Poratoa) is investigating proclems
of nuclear waste disposal. SpoKesaien ror Great Britain and hest Germany
gave accounts of the extent o± their country's comaitnent to nuclear
power and tae problems ot waste disposal. Tne necessity of coordinating
international cooperation in nuclear matters was underlined and an
informal organization was arranged at the Symposium. The International
Atoaic energy Agency (IAEA) is already involved in aspects ot waste
disposal; it considers the problem or enforcement ot disposal standards
more important than their devising, iu 19u5, the U. S. government
expects to begin operation of the first national site tor permanent
disposal of high level wastes. Projected nuclear industries will
produce 11 kinds of nuclear wastes whicfc must either i>e disposed of or
recycled. Disposal of high level waste is causing »ucn puolic concern.
Disposal of phased out reactor or reprocessing plants is also
discussed.
(t2) KKXWORDS: COSFEfiiiNCE; DISPOSAL; KNERril; EUfaOtE; FRANCE;'
SERHASY; SBEAT BRITAIN; INTER KATlONAi.; RADIOACTIVE; REGULATIONS;
SAFETY; STANDARD
(15) STIMS ACC.NO.: OOS37716
(18) DOC.ClT.i Experts mull over radioactive wa&te aisposal.
Chemical ana Engineering Mews, 54 (320) :21-23, Aug. 2, 197t>.
292
image:
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KADIOACTIVE WASTES
(1) SHIRS ACC.HO.: 03U598
(2) DOMESTIC: D (2) CATEGORY: 09 (<>) SUBJ.TYPi: I 110) FOB.
IBlHi 1976
(11) ABSTRACT: Different national approaches to the disposal of
nuclear waste are examined. It is estimated that the disposal oi
nuclear Haste by deep burial in stable rock formations will require 10
years of development die. A pilot plant disposal facility located in
Belgium is noted. The site, an underground cavity, is scheduled to be
ready for operation by 1979. In terms of French policies on nuclear
waste disposal, one issue being debated is whether to separate fission
products from actinides. It appears to be almost certain that France
will bury its waste in deep formation^ of rock salt or crystalline
rock. The target year for the first repository is 19bi>. in Italy, the
results of tests in impervious clay deposits are promising. A
processing pilot plant is scheduled tor mid 1980. The first
reprocessing plant in Spain is scheduled nor the late 1980*s, and it is
hoped that the first waste depository Hill ue ready by 1990. Spain is
considering the use of abandoned uranium mines, salt domes, and
anhydrite deposits for nuclear waste disposal. The most likely
possiblity for nuclear waste disposal in Sweden involves burial in
bedrock.
(12) KEYWORDS: BUHY; DISPOSAL; PliANCE; 1TAL1; MANAGEMENT;
BADIO ACTIVE; SUES; SKA IN; UHDERGSOOND
(15) SUMS ACC.HO.: OOS37642
(18) DOC.C1T-: Technology; sites sought fur nuclear waste disposal.
Chemical ana Engineering Mews, S4(33):23, Aug. 9, 197t>.
(1) SHIRS ACC.HO.: 038491
(2) DOMESTIC: f (2) CATEGORY: (it (2) SUBJ.TYPE: T (10) PUB.
IEAB: 1976
(11) ABSTRACT: The treatment of highly radioactive wastes consists
of converting the liquid solutions into a solid stable product. The
volume is decreased tenfold, so that a 1,000 Megawatt reactor produces
annually about 2 to 2. 5 cubic meters of solid waste. In rfest Germany,
there are three processes for solidifying highly active solutions. The
ultimate objective is to build a centralized solidification facility
for reprocessing radioactive waste with an annual capacity of 1,500
tons. The immediate objective is a pilot plant at tne Karlsruhe
reprocessing facilities. Solidified products are basically sate even if
geological conditions may turn unfavorable, fcorosilicate glass aay
offer an additional margin of safety. In Europe, the total volune ot
fission product concentrate from water reactor fuel reprocessing
facilities is presently arounu 100 cubic neters; therefrom about 30 en
m come from the Karlsrube plant. Additional 2,000 cu m come from fuels
of gas cooled reactors. A Foratom (foiua Atomique European) study,
presently in print, foresees a production of 9,000 en m oi concentrate
from water reactor fuels by 1985. (Text in German)
(12) KEYWORDS: CAtACli'Y; DISPOSAL; EUjtOPE; GEkMANJt; RADIOACTIVE;
SAFETY; SOLID; STABILIZATION; VOLUHfc
(15) SUMS ACC.MO.: OGS375JS
(18) DOC.CIT.: bokelund, d. , E. fewest, and H. L. Levi. behandlung
hochradioaktiver Abfaelle. (Treatment of nigniy radioactive waste. )
Atomwirtschaf t-A torn tech ink, 21 (7) : 352-3 57, July 1976.
(1) SHIRS ACC.HO.: 03BH90
(2) DOMESTIC: P (2) CATEGOH1: Oa (2) SUbJ.TltE: T (10) PUB.
1C BAR: 1976
(11) ABSTRACT: The largest volume or radioactive waste belongs to
the medium and weakly radioactive classes. In these groups waste water
represents the largest bulk. Vaporization is recognized as the most
effective process for decontaminating low and medium radioactive waste
waters, watery concentrates are consolidated to chemically and
physically stable products, thus further reducing the volume. Organic
liquid and solid wastes are equally reduced in voiume by additional
treatment. Methods of treatment are constantly undergoing improvements.
A diagram shows the nuclear fuel cycle from uranium ore mining and
primary enrichment through conversion plant (to convert tne concentrate
to uranium hexafluoride), to the main concentration plant, to fuel
element production, to nuclear power plant, to reprocessing ot
293
image:
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HAZARDOUS WASTE MANAGEMENT
irradiated fuel material, and finally to waste disposal. Another
diagraa shows the process or treatment of low and medium active waste
waters iron various nuclear installations {uranium ore dressing, fuel
eleaeiit production, power plant, reprocessing, isotope plant) tarough
the vaporization and distillation stages to tne concentrate production
and finally (after being solidified in ceaent or iiituaen) to disposal
places (salt Bines) . A detailed diagraa is given of the radioactive
vaste water treatment plant in the nuclear research center in
Karlsruhe. Solidification an ceneut and bitusien is cilso snown in two
diagrams . Noncoebus tible wastes (filters, glass, etc. ) are reduced in
voluee (1:3 to 1:7); in Karlsruhe, tor tne last 12 years, about 1500 cu
• of such wastes were reduced. They are stored in 200 liter carrels and
sealed with concrete. (Text in German)
(12) KEYWORDS: CHEMICAL; DISPOSAL; EV APOKA1ION ; GiKHANY; PHYSICAL;
PLANT-IBDOSTRIAi.; RADIOACTIVE; STABILIZATION; SIOhAGi;; I1 R£ AT Mi: Si'; HASTE
HATER
(15) STHS ACC.NO.: OOSJ7534
(18) DOC.CIT.: iiaehr, U . , ana * . Hild. .behafcdiung schwach- und
•ittelaktiver Ablaelle aus Kerntechnischen Aniayen. (Treatment of weak
and aediuai radioactive waste from nuciear installations. )
Atoavirtschaf t-Atomtechnik, 21 (7) :34t>-3;>2, July
(1) SH1BS ACC.BO.:
(2) DOBEST1C: ? (2) CATEGOKK: OS (2) SUbJ.TYi'E: o (10) PUB.
IBAR: 1976
(11) ABSTRACT: rhe govern*eut of *est Gereany has developed a
disposal systei for waste aaterials from water reactors. The systen
should be centralized and should Le fully operational cy «id 1960ls.
live syste« involves the following aspects of disposal: reprocessing,
fissionable fuel recycling, waste treataent, and waste disposal.
Everything should be ready so as to meet the needs of S>0,000 Megawatt
nuclear power capacity around 19»i>. Medj.ua and weak radioactive wastes
should be properly processed and disposed of in designated places, in
which the reprocessing takes place. Higoiy radioactive waste must be
stored in a consolidated fora. The final disposal of suca material
becomes the responsibility of the German Federal yovernaent. Tae
disposal technology should be teateu in tne rorner salt sine o.E Asse.
All research and develop»ent projects 111 the dosain of radioactive
wastes should be carried out within tne irdnevortc ot international
cooperation. The final disposal of highly radioactive waste should be
contemplated only after ail the tests at the pilot disposal grounds at
Asse are completed. For the tine ueiny the low volusie of solid! tied
highly radioactive waste (approximately 100 to 150 cu a per year)
creates no environsental hazards. (Text in Geraan)
(12) KEYWORDS: DISPOSAL; tiEJSMANj; PLArtNIMU; KADxOACl'lVB; SYSTEM
(1f>> STIBS ACC.NO.: OOS374455
Jib) DOC.CIT.: fiageii, M. , and fa. P. handi. Hadioaktive Aofaelle:
Arten und Hengen, Behandlun^, Lageruny. (nadiodctive wastes: types,
voluaies, treatment, disposal. ) Atomwartschaf t— Atoutechnik,
21(7) :338-J40, July 1976.
(1) SHIRS ACC.NO.:
(2) DOHESTiC: F (2) CATttiOKY: 09 (2) SUBJ.TY.fE: 1 (10) PJB.
YEAB: 1976
(11) ABSTRACT: The share of individual ty^es of waste in the total
amount of radioactive activity varit-s witnin a wide range, since over
9S percent of radioactive nuclides is available in a highly active
liquid form; these liquid wastes result from reprocessing of irradiated
nuclear fuels. From a 1500 ton/yr reprocessing plant, capable ot
servicing 40 nuclear power plants, an annual output averages 1,uOQ cu a
oi such liquid waste; the latter is reprocessed and solidified,, thus
reducing its volume. The largest £.hare by vo.Luue falls on priaary waste
products with weak, radioactivity. A table is given showing the voluae
(in cu «/yr) of wastes coning fron a IbOO ton reprocessing plant:
highly radioactive liquid fission products average 1,000; fuel eleaent
cartridges average B50; nediuu to active conct-ntrulet; average 1, 000;
weakly or Bediue active solid waste average S,000; licuid alpna
294
image:
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RADIOACTIVE WASTES
concentrates average 300; solid alpha waste averages ^00. The wastes
fro* fuel eleaent preparation (at a 1500 ton reprocessing plant) t
nonconbustible solid waste at 100; combustible solid waste at 2,000;
liquid waste at 500. Total anount ot was>te: 9,250 (with a total
plutoniun content, in kg/year, 300; and a total alpha activity, in
curie/year, 17,jOO,000). In 1975, taere were in operation in. West
Gernany: 10 nuclear power plants, a 35 ton per year prototype
reprocessing plant, a uranium processing plant, five mei elenent
producing plants, a snail isotope producing plant, and five larger
state and industrial nuclear research establishments. Tne total amount
of waste from all these facilities (in 1975) «as 2500 cu • liquid
concentrate, A official haa stated that the
deep continental geologic foraiations i.etnod appears most reasonanie
because such formations oifer the bett po&simlity of isolating
295
image:
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HAZARDOUS WASTE MANAGEMENT
radioactive waste from tne biosphere for the guarter of o Billion years
needed for the latter to .become innocuous.
(12} KilYKORDS: DISPOSAL; ECONOMICS; flAHAGEMiUiT; RADIOACTIVE;
THEATMEST
(15) STIBS ACC.HO.: OOS37<458
(18) DOC.CIT.: nuclear waste: soul searching. New Scientist,
71 (102) :2ba-2fa&. Aug. 5, 1976.
(1) SUBS ACC.NO.: 03o4l2
(2) DOMESTIC: F (2) CATEGORY: 09 (2) SUaj.TSPB: S (10) PUB.
YEAR: 1976
(11) ABSTRACT: The problems of transforming highly radioactive
fission product solutions from reprocessed fuel elements into a form
suitable for final deposit are described. As storage in liquid form
cannot be considered as optimum, a solidification of radioactive
residue is suggested. Criteria are given for tJie selection of suitable
final products. Vitrification, the incorporation of tne fission
products in glass, is generally suggested as the best method. Tne
development as well as various vitrification processes are described.
Chemical and technological problems affiliated with tne vitrirication
and manufacture of monolithic glass bjoclcs are pointed out and
alternative processes are described and compared.
(12) KEYWORDS: DISPOSAL; GMHANY; GLASS; PAOCESS; RADIOACTIVE;
SOLID; STORAGE; TBChHOLOGlf
(ti>) STIfiS ACC.NO.: OOS37<*M>
(Itt) DuC.ClT.: Ueiierl, «i. , P. tirziwa, aad DJ. van lieel. Chemical
and technological aspects of the vitrification of hiya level
radioactive Hastes. KerntechniK, Iti (bj : 272-277, June 1976.
(1) SHIRS ACC.MO.: G3J»2ob
(2) DOHESTIC: D (2) CATEGORY: u* (2) SUBJ.TY1>E: S (10| PUB.
YJSA8: 1976
(11) ABSTRACT: A new and improved procedure was developed for
determining leachabilities of proposed radioactive vaste forns. Finely
divided glass samples arc leached in slowing ueionizeti water; leached
ions are continuously sotbed on ion exchange resins to control ionic
quality, sorbed ions are eluted froa the resia columns for atoaic
absorption analyses, teachabilities measured by this procedure are
lower and more consistent than tnose made in stagnant water without
continuous ionic control. It is concluded that large variations in
leachabilities can be averted by using ion exchange resins to sorb
leached ions from solutions, benefits of the improved procedure are
discussed, as well as time: leachabxlity relationships and mathematical
data.
(12) KEYWORDS: AbSOBPflUti ; GLASS; ION; LEACh; M£ASUH£fl£lirS;
PROCESS; KADIOACTJ.VE; B£i,lN; STVkAGE; TBChSOLOGY
(15) STiaS ACC.NO.: OOS37310
(til) DOC.CIT.: fteily, J. A. , and B. A. Wallace. Procedure for
determining leachabilities at radioactive waste forms. Nuclear
Technology, 30 (1j :47-i»1, July 1976.
(1) SKIRS ACC.NO.: 03«217
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUaJ.TYPE: T (10) PUB.
YEAft: 1976
(11) ABSTRACT: One 01 tne major environaeutal concerns associated
with the projected increase in nuclear power generation is the
treatment and storage of disposal oi high level and transurauic
radioactive waste. 1'he model, entitieu AaRA* (Assessment Method for
Radioactive Haste Management) was developed by tne university or New
Mexico, and provides a detailed assessment methodology tor the short
tern as well as long term quantitative effects on the environment
resulting from the release of radionuclidts daring all phases of
radioactive waste management, operations. This model includes a fault
tree tor deteriinotion of release probabilities and tneir resultant
magnitudes, an environmental model for calculating transport of
radionuclides to man by environmental patfitrayti and an economic model
296
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RADIOACTIVE WASTES
for an evaluation oi associated damages. It ii> expected that full
impleaentation of this technology assessment model will aid tae U. S.
Environmental Protection Agency and others in evaluating the
radioactive high level and transuranic waste management programs.
(12) KEYWORDS: KBVIROKMEN T; ISOTOPE; MANAGEMENT; RADIOACTIVE;
SIMULATION; STORAGE; TRANSPORT; TkEATHENl'; UHlVERSI'J'r
(15) STIMS ACC.MO.: OOSJ7261
(1b) DOC.CII.: Lotjan, s. E- , and S. H. Goldberg. A radioactive
waste management assessment aodel. in Ott, N. R. , o. Albrecht, and B.
Clark, eds. Proceedings; the Conference on invironnental Modeling and
Simulation, Cincinnati, Oh, Apr. 19-22, 1976. Environmental Protection
Publication EPA-600/9-76-016. Washington, 0. :>. Environmental
Protection Agency, July 1976. p. 199-Z03.
(1) SHIRS ACC.MO.: 03&216
(2) DOHEST1C: D (2) CATEGOBlf: 09 (2) SUBJ.TYPE: S; I (10) PUB.
XKAfi: 1976
(11) ABSTRACT: A mathematical model has been developed to predict
radionuclide levels in the Great Lakes due to nuclear power generation
in the United States and Canada. The calculations have keen used to
verify the feasibility of proposed international water quality
objectives lor radioactivity in the Lanes. Dose rates and doses to
reference Ban froa the ingestion of Lake waters are predicted based on
expected future power generation in this region. The liquid effluents
discharged into the Great Lakes rrom nuclear power plants and other
nuclear facilities, such as fuel reprocessing plants, are of particular
interest in this regard since some oi the entrained rudionuclides have
relatively long half lives. Results are given in terms of rauionuclide
concentrations in each lake and the dose rates and doses ensuing from
continuous, long tern ingestion or system waters. Kith the model
described, it is possible to obtain analytical solutions for the
coupled differential equations describing these quantities as a
function of time. However, a FORTRAN computer program has been employed
to reduce the calculational effort required.
(12) KEIiORDS: CANADA; COttPUTKR; ISOXuPE; MATHEMATICAL HOUEL;
PROJECTION; QUALITY; uADlOACTlVE; TkANSPOKT; OS; HATER; WATEHWAI
(15) STIflS ACC.NO.: OOSJ7i:60
(18) DOC.CIT-: Sullivan, R. E. , and u. h. Eliett. Hadionuclide
transport in the Great Lakes. In ott, H. R. , 0. Albrecht, and fi.
Clark, eds. Proceedings; the conference on Environmental Modeling and
Simulation, Cincinnati, OB, Apr. 19-2^, 1976. Environmental Protection
Publication EPA-600/9-76-016. hashington, U.S. Environmental
Protection Agency, July 197t>. p. 161-165.
(1) SHIRS ACC.NO.: 03eOi1
(2) DOMESTIC: F (2) CATEGORY: 09 (2) SUBJ.TYPE: T (10) PUB.
XEARi 1976
(11) ABSTRACT; The use of radioisotope tracer techniques for the
disposal of radioactive solvent waste is addressed. An apparatus xs
described that was constructed to investigate tne possibility of
decontamination at the source by nasaing radiocaenicals out into water
and discharging them into the normal drainage system in d hignly
diluted form. The apparatus consists of a stainless steel funnel fixed
by means of a silicone rubber bug into the neck of a glass bottle. The
bottle stands by a sluice or drain outlet into which overflow is
discharged. Waste solvent aadea to the apparatus accumulates in the top
of the bottle, and water liows througn the solvent dovn the funnel wall
forming an interface at which water soluble substances are extracted.
Hashed solvent can be withdrawn fro* the apparatus via a light solvent
outlet. Solvents with density greater tnan that oi water will
accumulate at the bottom of the bottle and may oe withdrawn via a heavy
solvent outlet. Washed solvent with reduced radioactivity can be
disposed of in the usual way. Typical rates or radioactivity removal
297
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HAZARDOUS WASTE MANAGEMENT
are presented, and certain disadvantages of the apparatus are
discussed.
(12) KEYWORDS: DILUIIOH; DISPOSAL; BQUIPMBlIt; RAD10ACTHB; SOLVENT;
TECHNOLOGY; BATBH
(15) STIMS ACC.HO.: OOS37095
(18) DOC.CIT.: Dean, b. , and W. i'. Baker. The disposal of
radioactive solvent waste. International Journal of Applied Radiation
and Isotopes, 27 (3) : 185-186, Bar. 1976.
(1) SUIfiS ACC.SO.: 037987
(2) DOHESTIC: F (2) CATEGORY: 09 (2) SOBJ.TYPE: T (10) PDB.
YEAR: 1976
(11) ABSTRACT: The report discloses the results of an investigation
into the requirements for securing land for underground radioactive
waste disposal sites, particularly the determination of -the size of the
land required for security of the residents in the surrounding area. As
a result of the investigation, it also proposes a Method to determine
the size of the disposal site ground and a method for institution of an
area for United use of the lane. Distribution of radioactive nuclides
in underground waters and minimal allowable size for the disposal site
and United use of the land are investigated, and it is concluded that
in spite of various variable environmental parameters such as the
velocity of the ground water, diffusion coefficient, equilibrium
distribution factor of strontium 90, the determination for the minimal
allowable size for a radioactive waste disposal site can be calculated
and that institution of an areas tor limited use of land is desirable
for further assurance of security. (Original text in Japanese)
(12) KBYHOBDS: COMTAMISATE; DISPOSAL; FACILITY; GROUND BATEB; LAUD;
PUBLIC; RADIOACTIVE; REGULATIOHS; BKSEARCH; SAFETY; SITES; SIZE;
UNDERGROUND
(15) STIHS ACC.SO.: OOSJ7031
(18) DOC.CIT.: Inoue, Y» , and S. Horisava. Hoshasei haikibutsu
chichu shobunjo no rittchi ^oken (Land requirements for a radioactive
waste disposal yard). Hihon Genshiryoku Gakkai Shi, 1o(5):304-312, Hay
30, 1976.
(1) SilRS ACC.KO.: 037892
(2) DOHEST1C: D (2) CATEGORY: 09 (2) SUBJ.T2.tE: S; T (10) PUB.
IEAR: 1976
(11) ABSTRACT: A practical method is presented for calculating
radioactivity buildup in collection tanks for nuclear power plants.
Fifty radioisotopic properties used in raawaste analysis are provided,
along with filter, demineralizer, and evaporator properties. It is
noted that the treatment of liquid raduaste in a nuclear power plant
generally includes collection of the liquid in storage tanks and
processing it through a combination of filters, demineralizers,
evaporators, and other devices. During collection and processing,
activity in the tank has to be determined. This is necessary for
calculating shielding thickness and for determining radiation exposure
to operating personnel. Although specific empnasis is placed on
radiation levels in the collection tank of a radwaste system for a
1F100 HKe boiling water reactor plant, the information can be used to
obtain approximate values for other nuclear power plants. Equations are
given which govern the rate of activity buildup in a tack.
(12) KEYWORDS: AHALYSIS; COLLECTION; DATA; ISOTOPjS; LIQUID;
HATHEHATICAL MODEL; PLABT-lNDUS'fRIAL; RADIOACTIVE; STORAGE; TANK
(15) STIMS ACC.NO.: OOS36936
(18) DOC.CIT.: ABIT, S. j. Radwaste buildup in tanks. Power
Engineering, 80(6):64-67, June 1976.
(1) SUIRS ACC.HO.: 037860
(2) DOBESTIC: D (2) CATEGORY: 09 (2) SUBJ.TJPE: T (10) PUB.
TEAR: 1976
(11) ABSTRACT: The operation of wiped film evaporators to
concentrate aqueous radioactive waste is detailed. Wiped film
evaporators provide sufficient waste volume reduction in a single pass
298
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RADIOACTIVE WASTES
to yield a product that solidifies completely upon cooling. They are
snail enough to be mounted in or over waste tanks and can be moved tram
tank to tank. As a result, the existing waste concentrate transfer
system could be eliminated. Concentration is coapieted in one pass
without recirculation. because there is no liquid level, elevation in
boiling temperature due to nyarostatic head it, eliminated, because only
a saall amount of material is in process at any tiae, holdup ti»e is
extremely short. These features aa/ce a wiped film evaporator suitable
for handling higniy viscous or roauy waste materi«tls ana solutions
containing precipitated tol^d aateria*. Tae results ot tests are
presented which denonstrate that wiped film evaporators are also
suitable for concentrating radioactive waste solutions.
(12) KE**ORDS: COKCENTKAT10S; DiSlGN; EG.UIPKE&T; EVAPORATION;
HAlNTfiNAUCK; MOVAfaLfi; RADIOACI'IV J£; RiuuU CTION; Ti-CrfNOLOGi ; VOLUME
(15J STIB5 ACC.SO.: OOS36904
(1tt) BOC.CIT.: Goodlett, C. Js. tutting evaporators to vorfc:
concentration of aqueous radioactive »aste. Cheaical Engineering
Progress, 72 (<*} ;63-b4. Apr. 1976.
(1) SHIRS ACC-SO.: G376U8
(2) flOBESTiC: D 12) CATEGORY: 09 (2) SUttJ .I'lTPE: T (10) PUB.
IEAB: 1976
(11) ABSTRACT: Equipment nua methods 01 uisposai of radioactive
wastes are discussed. Types oi waste include combustible wastes,
commercial radioactive isotope wastes, reactor oft gases, spent fuel
processing wastes, anc tritium. Mecnous used xnclude incineration, long
term storage, salt deposit, land uunal, and deep well disposal.
(12) KEYWORDS: SEEP WKLL; DISPOSAL; li^UIPMKNT; dAZAMDOUS;
XMClSEfiAtiON; INDUSTRY; LAJS^j; KAkiOALi'i V£; oALT; ^fOBA«£
(ti) STIHS ACC.HO-: OOS36a52
(lb) DOC.CIT.: Powers, f. w. aluciear industry wastes, in: aow to
Dispose of Toxic Sucstances and Industrial wastes, aoyes Data
Corporation, 197b, 497 p. (p. 273-3UOJ.
(1) ShIRS ACC.SO.: 037005
(2) 1>OBEST1C: I) (2) CATEGOKJt: (J-J (2) SUBJ.rifPE; T (1") PUB.
I BAB I 1976
(11) ABSTRACT: A discustdon ol acceptable aethods which aay be used
to dispose of specific inorganic chencai substances is presented. The
cnemicals are: alKali and ammoniua liuorides, aiuminua, barium and
cadaium fluorides, aiuminua fluoride cauufacture, alUKinugi oxide,
aanonia plant eftluents, ammonia soda plant effluents, ammonium
chloride ana nitrate, amnoiiiufli percniorate ana other oxidizers,
aaaoniui persulfate, antimony fluorides, antiaony sulfates and
sulfides, arsenic trichloriae, asbestos, toeryllium ana berylliua
compouuus, boric acid manufacture, i,ro»ic acia, bromine, calcium
carbide, calciua hypochiorite, caiciua pnospnaie, caustic chlorine
production wastes, chlorate phosphorus mixtures, chlorosulfonic acid,
carome pigments manufacturing wastes, chromium saits, copper hyuroxide
and sulfite sludges, cyanidt-s, hydrozine, hyda^oic acid, hydrofluoric
acid manufacturing wastes, hydrogen cyaniae, lead, lead oxide, lead
salts, aiagnesiua chlorate, oxiae aiiu oaits, nic*.ei antinoniae, arseniae
and selenide, nickel sulfate, caiori.de and citrate, nittogen oxides,
phospnate slimes, pnoaphoruii, phosphorus chlorides, phosphorus
pentasulfide, seieniua, sodiua a2ide, soaium chlorate, sodiui
hypochorite, sodiua metal, sodium perchiorate, sodiun silicofluoride
manufacturing wastes, sulturic acid, thalluim compounds, titanium
dioxide, and titanium tetrachioriae procat,s wastes.
(12) KEYWOKDS: ALUBlSUB ; AKHON1A; Ai,b£Sroi; CAJLUlUH; CHtMiCAL;
CHLORIDE; CUROHIOfl; lilSPOSAi.; UA^AttbOOb; INKUbTHY; INOHGAHIC; NITHOGEN;
PHOSPHATE; PHOSPHORUS; PLANf-i»I)UST«lAL; SELtfclUB; SOUIOH
(15) ST1HS ACC.NO.: OOS3684&
(IB) DOC.CIT.: Powers, P. h. inorganic chemical industry wastes.
In: How to Dispose of Toxic substances and industrial Hastes, Noyes
Data Corporation, 1976, 497 p. (p. 22/-/:57).
299
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HAZARDOUS WASTE MANAGEMENT
(1) SHIRS ACC.MO.: 037601
(21 DOflESTIC: D (2) CATEGOKl: 0* (2) SUiiJ.TYPE: T |10) PUB.
TEAR: 1976
(II) ABSTRACT: A aethod is presented for treating waste gases
containing radioactive contanination, particularly krypton and xenon
nuclides. The waste gas streaa to be decontaainated is tirst conducted
through an enrichment systes Kherein the waste gas stream is divided
into two partial streams, one of which is substantially tree froa the
radioactive itpurito.es and constitut.es the poor gas fraction an.d
another of which constitues the rich gas fraction. The poor gas;
fraction is discharged, at least in part into the atmosphere wfi.ile the
rich gas fraction is led into an activated carbon delay path whose
output is discharged either directly or indirectly into the atmosphere.
Apparatus for carrying out the method is also disclosed.
(T2> KBIiOKDS: ACTIVATED LAHbON; DESIGN; EQUItBttlT; GASHES;
GERMANY; PATENT; RADIOACTIVE
(15) STIHS ACC.KO.: OOS3664t>
(18) DOC.Cir.: stuapf, w. , u. ^utiser, and h . Juentgen. Hethod and
apparatus for treating waste gases containing radioactive impurities,
particularly krypton and xenon uuclides. U. S. Patent No. 3,9t>3,460.
Issued June 15, 1976.
(1) SBIBS ACC.SO.: 037600
(2) DOBEST1C: D (2) CATEGOBX: 0* (2) ijUBJ.I'Ii'E: I (1u) POB.
XEARi 1976
(11) ABSTRACT: A process ior reduction in bulk of hignly
radioactive wastes is discussed, cat-ion exchange aaterial ot the
hydrous oxide type is used. Titanium is the preferred metal but
niobinm, zirconiua, and tantalum nay also be used with sodium usually
the exchangeable ion. Of the two principal streaas leaving the process,
one will be highly radioactive titanate/zeolite ceramic and the other a
slightly radioactive, transuranic-free sodiua nitriate waste. Hope is
expressed that the Handford wastes can be successfully reduced in bulk.
utilizing this method.
(12) KEIiOHDSI CHEHlCii; DISPOSAL; ECUSOHICS; IliUhGAMIC; 1QB
EXCHAMGE; PROCESS; RADIOACTIVE; KiDUCTlON; BKS1S; T8EATKEST
(tb) STIHS ACC.SO.: OOS36644
(18) DOC.CIT.: Anon. New process consolidates radioactive wastes.
Cheaical and Engineering News, i>U:32-33, Jan. 1976.
(1) SHIRS ACC.NO.: 0375^6
(2) DOHESXIC: D (2) CAl'EGOKX : 0» (2) SUBJ.TYPE: T (10) PUB.
XEARt 1976
(11) ABSTRACT: The use of a wiped fila evaporator for hign level
radioactive waste is explored. A pilot scale wipea Him evaporator is
being evaluated for concentrating high radiation level liquid waste
froa Purex type nuclear fuel recovery processes. The evaluation is
being carried out at fiattelle's Pacific Northwest Laboratories and is
sponsored by the Energy Research and Development Administration. The
goal of the evaluation prograa is to deaonstrate a commercially
feasible technique for fixing high radiation level waste in a stable
solid. The wiped file evaporator is being evaluated as part of a glass
Baking systea, with the feedstock oeing siauiated Purex type waste. Tne
evaporator used in testing is a tapered, horizontal drum like unit with
about 5 sq ft of heat transfer surfaces. Operation of the evaporator is
detailed, with the evaporator drua being heated by a steaa jacket,.
Tabular data are provided on typical simulated waste leedstocn
coapositions, and it is noted that the performance of the evaporator
differs slightly for each feedstock COB position. Perforiance in general
is related to product concentration as a function of jacket temperature
and feed flow rate. The evaporator lesulted in the production of
concentrates up to 60 weight percent total splias. It is concluded that
300
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RADIOACTIVE WASTES
tae device is efficient for highly concentrating simulated waste
slurries.
(12) KEYWORDS: OPPOSITION; CONCL«IKAi'IOH; JSQUlPBENi'; EVAPORATION;
FUEL; GLASS; HEAT; LIQUID; PROCESS; RADIOACTIVE; BECLAHATION; ROTATING
DBUB; S1HULATION; SLOHBK
(IS) STXHS ACC.NO.: OOS36oOO
(16) DOC.CIT.: Dierks, R. B. , and u. f. iioiiner. wiped film
evaporator tor high level wastes. Chemical Engineering Progress,
72(») :61-62, Apr- 1976.
(1) SHIRS ACC.MO.: 037519
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUbJ.TYPE; X (10) PUB.
TEAR: 1976
(11) ABSTRACT: Solid radioactive waste is incorporated in glass,
ceramic or basaltic blocks which are conditioned in waste waters or
sludges prior to placement in nonpolluting ultimate storage. The
conditioning has the dual benefit of reducing the radioactivity of the
radioactive waste and of purifying the waste Mater or of purifying and
facilitating the filterability of the sludge. Such purifying is
enhanced by concurrent treatment with oxygen or an oxygen-containing
gas and/or with a substance which is readily reduced to radicals.
(12) KEYWORDS: CEBANIC; GUNMAN*; GLASS; ILLUSTRATIONS; OXYGEN;
PATENT; PURIFICATION; RADIOACTIVE; SOLID; TREATHEMT
(15) STIHS ACC.NO.: OOS36563
(18) DOC.CIT.: HiId, M. , H. Krause, and K. schefrler. Conditioning
highly radioactive solidified waste. U. S. Patent No. 3,971,717. Issued
July 27, 1976.
(1) SHIBS ACC.HO-: 037514
(2) DOHESTIC: D (2) CATEGORY: 0* (2) SUBJ.TYPK: T (10] PUB.
TEAR: 1976
(11) ABSTRACT: A method ot and apparatus for the purification of a
liquid contaminated with radioactive substances is presented. The
liquid is fed into an evaporator which is connected to a column having
a multiplicity of supposed plates or floors. The vapor generated in the
evaporator is guided through a washing or scrubbing liquid uniformly.
The washing liquid at the floors is deflected a number of times in such
a manner that the washing liquid itself and together with the droplets
entrained by the vapor is uniformly admixed and the washing liquid
subjected to a constant intake of the radioactive substance. The
concentration of the radioactive substance is reduced in an economical
manner.
(12) KEYWORDS: EQUIPMENT; EVAPORATION; ILLUSTRATIONS; LIQUID;
PATENT; PURIFICATION; RADIOACTIVE; REDUCTION
(15) STIRS ACC.NO.: OOS36558
(18) DOC.CIT.: flende, H. Method and apparatus for tne purification
of a liquid contaminated with radioactive substances. U. s. Patent No.
3,969,194. Issued July 13, 1976.
(1) SHIRS ACC.NO.: 037449
(2) DOHESTIC: D (2) CATEGORY: 09 (2) SUBJ.TYPE: G (10) PUB.
YEAR: 1976
(11) ABSTRACT: According to a new report to Congress from the
General Accounting Office entitled "Improvements Needed in the Land
Disposal of Radioactive Hastes", there is no guarantee that existing
land disposal sites receiving a wide variety of low-level radioactive
wastes will not create a public health hazard r»y reason of the wastes
migrating from their original burial sites. Tne GAO found both a lack
of geological criteria for site selection and a lack ot data for aost
existing sites. Tne report caxls tor additional geohydroiogical
evaluations and research to estaolisn criteria to insure that future
sites are selected on the basis of detailed studies. Gaps in data
referred to by GAO are mostly ground-water related and include lack of
data concerning infiltration ground-wuter movement, the extent of rock
fractures, and connections netween shallow ana deep acquiters. The GAO
report is supported by EPA studies which show that commercial burial
3d
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HAZARDOUS WASTE MANAGEMENT
grounds are not sufficiently analyzed before licensing by various
federal agencies.
(12) KETHOHDS: ANALYSIS; bOBJ; COMMERCIAL; CRITERIA; DISPOSAL;
GKOLOGIC; GfiOOKD HATER; HYDROLOGY; LICENSE; KAD10ACTHE;
RBSPOHSIBILITY; SITES; TRANSPORT
(15) STIBS ACC.BO.: OOS36493
(18} DOC.CIT.: Gillies, N . p . GAO finds buried radioactive wastes
on the move at some sites. Ground Water, 14(3) :174-175, Feb. 1976.
(1) SHIES ACC.SO.: 037302
(2) DOMESTIC: D (2) CATEGORY: 0* (2) SUbJ.TIPE: T (10) Jr-UB-
YEARi 1976
(11) ABSTRACT: The operation of a vacuum evaporator-crystallizer to
handle radioactive Baste is detailed. The vacuuB
evaporator-crystallizer is being used by Atlantic Richfieid to convert
high level radioactive waste solutions to solid fonts suitable for
storage. Approximately <*. 5 Billion gal ot less mobile salt cake,, plus
about. 4 Billion gal of concentrated liquor, nave been generated from
nearly 23. 5 Billion gal of waste processed. The salt cake is composed
primarily of sodium nitrate and sodiun carbonate, plus soae
nondrainable trapped liquor. Atlantic Richfield operates the waste
aanagaenet program for the Energy Research and Development
AdBinistration (EKDA). Problems associated with prograa operation are
noted, and the construction oi a second vacuum evaporator-crystailizer
unit is described. Perforaance aspects of the vacuua
evaporator-crystailizer are reported in relation to iihDA standards.
Four mechanical difficulties of the unit are identified: pump
vibration, broken dip tube, plugged slurry line, and lou exchange
column, future processing plans of Atlantic itichfield are discussed,
and the development of a computerized evaporator-crystallizer process
•odel is described.
(12) KEYWORDS: COHHERCIAL; COMPUTER; EQUIPMENT; EVAPORATION;
ILLUSTRATIONS; L1QOOR; BAHAGEttENT; PLASNISG; PfiOBLEHS; PfiOGRAH;
RADIOACT11E; REDUCTION; SALT; SOLID; SOLUtolLITSf; STOKAGK; VACUUH;
VOLOHB
(15) STIBS ACC.no.: OOS36347
(18) DOC.CIT.: Petrie, J. C. , fe. I. Donovan, and a. i,. Van 3er
Cook. Putting evaporators to work: vacuum evaporator-crystallizec
handles radioactive waste. Chemical Engineering Progress, 72(4):65-71,
Apr. 1976.
(1) SHIES ACC.HO.: 037163
(2) DOBBST1C: D (2) CATEGORY: Oi (2) SOBJ.'rKFE: S; T (10) POu.
XKAR: 1976
(11) ABSTRACT: As part of the radiation quality assurance program
conducted by the U. S. Environmental Protection Agency, calibrated
radionuclide solutions are distributed to participating laooratones
for instrument calibration and yield determinations. Laboratory
performance studies involving the analysis of radionuclides in
environmental media are also conducted, and a summary is given of tne
results of the water cross-check program for 1974. Examination of these
results reveals that gross beta is the most difficult (44 percent
within the control limits) for the laboratories to analyze. These
results indicate the need for improvement in analytical procedures for
the radionuclide studies. (Document retained in SNIRS library)
(12) KEYWORDS: AUALYSIS; CMEHICAL; COMPARISON; CUUfKOL; flATA; EPA;
ISOTOPE; LABORATORY; METAL; PtfOGKAB; DUALITY; RADIATION; HATER
(15) STIBS ACC.UO.: OOS36208
(18) UOC.CIT.: Jarvis, A. N. , H. F. SmieciusJti, and D. G.
Easterly. The status and quality of radiation measurements oi water.
Environmental Protection Publication bOO/4-76-017. Las Vegas, NV, U. S.
Environmental Protection Agency, Apr. 1*76, 2ts p. (Environmental
Bonitoring Series) (Distributed by National Technical Iniortation
Service, Springfield, VA)
302
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RADIOACTIVE WASTES
(1) SKIES ACC.80.: 037156
(2) DOMESTIC: D (2) CATEGORY: 0* (2) SUfaJ.TYPE: S; T (10) PUB.
YEAR: 1976
(11) ABSTRACT: the relative risks to man from radionuclides
released to the environment depend heavily on taeir accumulation or
concentration by aquatic organisms. Tne organisms which accumulate
those radionuclides present in the environment may tie useful as
indicators for environmental monitoring purposes. In addition, these
organisms nay be directly in rood chain pathways to humans. Literature
is reviewed and summarized in regard to biological concentration of
radionuclides in freshwater and marine enviroments. Concentration
factors tor elements round in organisms are tabulated for plants,
invertebrates, and tish in aarine and freshwater environs. Literature
is also reviewed on models developed to calculate the possible
radiation dose delivered to humans iron radioaaclides released into
aquatic environments. Tae model approaches summarized range rrom simple
generalized forms which, at best, give order of magnitude estimates to
detailed models for a specific area which may be used to guide waste
discharge practices. (Document retained in SWISS licrary)
(I2i KEYWORDS: BIOLOGICAL; coNCi&TRATioh; DATA; ENVIRONMENT; FISH;
FOOD; ISOrOPiS; LiTERATOfatf; MATHEMATICAL MODEL; MOHirOB; POLLUTION;
BADIATIOK; VEGETATIOM; WATERWAY
(161 STlflS ACC-NO.: 00536^01
(1b) DOC.C1T.: Patzer, R. G. Concentration factors and transport
models tor radionuclides in aquatic environments: a literature report.
Environmental Protection publication t>00/3-76-034 . Las Vegas, NV, u. s.
Environmental Protection Agency, flay 1976, 64 p. (Ecological Research
Series) (Distributed by National Technical Inlormation Service,
Springfield, VA)
(1> SHIRS ACC.HO.: 037010
(2) DOMESTIC: D (2) CATEGORY: Oi* (2) SUbJ.XYPE: S; I' (10) tOB.
YEAR: 1976
(I1J ABSTRACT: The conversion or liquid high level radioactive
wastes into granular materials ±or dispersion into metal matrics is
addressed, based on work, carried out t>y the Eurochemic Company in
Belgium. The operation ol Eurocheaic plants has resulted in tne
accumulation of two types of high level liquid wastes: (1) concentrated
fission product solutions fro* highly enriched uranium processing; and
(2) concentrated fission products froa low enriched uranium processing.
Eurochemic's low temperture solidification process, waicn is i>asea on
calcination to oxide granules by a iiuiu bed calcination technique,
involves the conversion of nitrates in high level wastes to yranular
phosphates in the presence of aluminum at low tempratures. sufficient
aluminum nitrate and a stoichiometnc amount of phospnoric acid are
added to the waste teed solution, sprayed into a stirred bed reactor
kept at about 550 degrees C, and pretiiled with aluminua phosphate
particles. The granular phosphate product shows a leachability for
cesium and strontium that is »ore than a thousand times lower tnan that
of corresponding oxide calcines. The glass bead production process is
detailed. Three types of metal anoys have ceen selected for
investigation with reyard to their suitability as emcedding material
for different nigh level waste solids: (1) lead alloys melting in the
temperature range from 2tO to 320 degrees C; (2) zinc alloys melting in
the range from 400 to 500 degrees C; and (3) aluminum alloys melting in
the range from 550 to 660 degrees C.
(12) KEYWORDS: iLUMJNUfl; ASSOC; CJiLGIUM; COHCEftl'RAi'IOK; CUHtfEBT;
FL01D1ZED BED; I8DOSTHY; iNVESTiGATiOtt; L£ACH; LIQUID; ailPAL;
PHOSPHORUS; PROCESS; RADIOACTIVE
(15) SUMS ACC.SO.: OOSJ6055
(18) DOC.CIT.: van Geel, J. M. , U. Eschrich, aua t. J. Detilieux.
Conditioning high level radioactive wastes. CUe»icai Engineering
Progress, 72(3):4y-51, Mar. 197o.
(1) SilIRS ACC.NO.: 037009
(2) DOMESTIC: D (2) CAi'EliORX: Of (2) SUBJ.TYPK: T (10) PUB.
YEAR: 1976
(11) ABSTRACT: A technique for tne continuous vitrification of high
level radioactive wastes is described tftat is being developed by the
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HAZARDOUS WASTE MANAGEMENT
Preach Atomic Energy Commission. A facility aas been designed to
convert all fission products generated at a nuclear reprocessing plant
into solid glass aaterial. The first radioactive test run is scheduled
for July 1977. Two steps are involved in the vitrification process: (1)
continuous calcination; and (2) continuous glass makiug with the
calcined product and suitable aduitives. Thr^e types of high leveri
radioactive wastes will be reprocessed. One type is related to aaterial
testing reactor spend fuels, and the other two types are related to
natural uranium spent fuels. The fission proctact conversion facility
has tuo main sections (vitrification and storage areas), and it is
anticipated that the storage area will oe large enough to dispose' of
glass resulting from existing stored solutions and from nuclear
reprocessing plant production for the next 10 yrs. It is noted that the
storage area can be expanded to meet additional capacity requirements.
(12} KEYWORDS: CAi£IOa; CERAJ1IC; CONVERT; DhSlGK; DISPOSAL;
FACILITY; FRANCE; FUEL; FURNACE; GLASS; PftOCfiSS; jIOACXiViS; STORAGE
(1b) STIHS ACC.NO.: 0033605^4
(Ib) DOC.CIT.: Bonniaud, R. , and C. Soabret. Continuous
vitrification of radioactive wastes. Chemical Engineering Progress,
72(31 :<»7-4b, Bar. 1976.
(1J SHIRS ACC.NO.: 036960
(2) DOHESTIC: D (2) CATEGORIC Oy U\ SUBJ.TKfE: S; T (10) ?Ub.
XEA8: 1976
(11) ABSTRACT; A sethod and apparatus reduces the amount of
radioactive solids resulting iron the filtration of patticulate
contaminants from liquid in a nuclear reactor plant. A filtration
system includes a pre-fiiter comprising a sheet filter aediuai tnrougn
which the reactor liquid passes to remove relatively large particulate
contaminants for storage or disposal. The reactor liquid is then passed
through a bed of granular filter medium to accunulate substantially all
the previously non-filtered contaminants and thereby provide a
clarified liquid suitable for reuse in tht reactor. Backwash liquid is
flowed through the granular filter «ea to remove ana entrain the
accumulated contaminants into a slurry which is received oy a reservoir
where the slurry is maintained quiescently to settle the contaminants.
Removal of liquid fro» the reservoir concentrates the contaminants for
Storage or further processing, without the necessity of large
quantities of filter aids that would increase the quantity of
storage-requiring conta»iuated solids.
(12) KEYBO&DS: COLLECTION; CONCENTRATION; COS TABINAI'E; EgUlPHENT;
FXLIE8; ILLUSTRATIONS; LIQUID; PAJESi'; PROCESS; RADIOACTIVE; REIJUCTION;
SfiTliEBE*!'; SLURRX; SOLID; STORAGl
(1&) STIMS ACC.NO.: OOS36UOi>
(1«) DOC.CiT.: Hirs, G. Hydrowation filter Coapany. aethod ana
apparatus for treating liquid contaaifcated with radioactive partxculate
solids. U. S. Patent mo. 3,9t>2,07b. Issued June b, 1y76.
(1j SWIRS ACC.NO.:
(2) UOHEST1C: D (2) CATEGORY: Ui* (Z) SObJ .TYi'E: T 110)
IEAB: 1S76
(11J ABSTRACT: Apparatus it; disc^osea for disposing of radioactive
waste materials by placing them into a steel drua together with cement
and water, mixing the content^, and then stormy the drua for a period
of time to permit partial decay ot radioactive material's. Also
disclosed are remotely controlled apparatus for fjJ.ling, closing and
agitating the drum including special Beans tot unscrewing a cap froa
the drun, for holding the cap during tilling, and for replacing tne cap
after filling.
(12) RECORDS: i»ECOBPOSK; Ju£i,lGN; LilSPOiAL; EQ01PKKNT;
ILLUSTRATIONS; PATENT; RADIOACTIVE; SiOttAUE
(15) STIftS ACC.No.: OOS3S669
(18) DOC.Cir.: Stoc*., A. J. , I), ii. Chris>t.ofer, and J. E. Brinza.
Stock Equipment company. Apparatus tor inserting closure neans into a
container. 0. S. Patent No. 3,9j2,97a. Issued Jan. 20, 1976.
304
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RADIOACTIVE WASTES
(1) SHIRS ACC.NO.: 036515
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SOBJ.TIPE: S (tO) PUB.
XElfi: 1976
(11) ABSTRACT: After a first extraction of an aqueous nitric acid
solution of spent nuclear fuel by a suitable organic solvent and a
first washing of the resulting organic phase t»y an aqueous solution to
remove tritiated water, the organic phase is submitted to a second
•ashing with a volume ox dilute aqueous solution of nitric acid free
fro* tritium, said volume being substantially smaller than that of the
organic phase, whereby the organic phase is rendered substantially
tritium-free and contamination by tritium in the following stages of
the process is avoided. (Author Abstract)
(12) KETBOBDS: ACID; CONTAMINATE; DESIGN; FUEL; ILLUSTRATIONS;
ORGANIC; PATENT; PROCESS; RADIOACTIVE; SEPARATING; TREATMENT; HASH
(15J ST18S ACC.NO.; OOS35559
(18) DOC.CIT.: Bernard, C. Saint-Gobain Techniques Nouvelles,
Courbevoie, France. Treatment of irradiated nuclear fuel. U.S. Patent
Ho. 3,954,654. Issued nay 4, 197t>.
(1) SBIRS ACC.BO.: 036308
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUBJ.TY.PE: G (10) PUB.
IEAH: 1976
(11) ABSTRACT: Witnesses before a House Subcommittee contend that
radioactive waste migration has resulted from lack of adequate
planning, hydrogeological evaluation, and radiation monitoring at
disposal sites. Although radioactive debris does not presently pose a
serious health hazard, spokesmen agree that greater care must be taken
to establish stringent criteria lor licensing federal and commercial
disposal grounds. An interagency task force is already meeting to
develop a national radioactive waste disposal plan.
(12) KEY WORDS: DISPOSAL; GOVERNMENT; HABAt-EflENT; RADIOACTIVE; US
(15) SUMS ACC.NO.: OOS35353
(18) DOC.CIT.: Anon. Radioactive waste disposal inadequate.
Chemical and Engineering Hews, 54{9):5, 1976.
(1) SHIRS ACC.NO.: 036202
(2) DOMESTIC: D (2) CATEGORY: 0* (2) SUBJ.TYPE: T (10) PUB.
YEAR: 1976
(11) ABSTRACT: The D. S. Nuclear Regulatory Commission requires
that liquid waste remaining alter the reprocessing of spent nuclear
fuel be converted to a solid form before storage or shipment. Two major
solidification processes, fluidized bed calcination and spray drying,
produce a 'calcine* which is granular and contains a high proportion of
"fines" which are undesirable. A feasibility study was performed to
determine whether nuclear waste calcine and a crystalline ceramic
matrix can be fabricated by hot pressing into a composite waste form
with suitable leaching resistance and thermal stability. The addition
of small quantities of low viscosity glass produced a suitable
composite. Additional studies are suggested to: optimize the matrix;
optimize waste/matrix ratios; use modified calcine. Engineering
feasibility must also be determined.
(12) KEYWORDS: CERAMIC; CONVERT; DRYING; FINE; FLUID1ZED BED;
GLASS; LEACH; LIQUID; PROCESS; PRODUCt; RADIOACTIVE; bOLID; STORAGE;
THEBHAL; TRANSPORT
(15) STIMS ACC.NO.: OOS35247
(16) DOC.CIT.: McCarthy, G. J. , and fl. T. Davidson. Ceramic
nuclear Haste forms: 11, a ceramic-waste composite prepared by not
pressing. Ceramic Bulletin, 55 (2):190-194, 1976.
(1) SHIRS ACC.NO.: 036114
(2) DOMESTIC: D (2) CATEGORY: Ob* (2) SUBJ.TYPE: S; T (10) PUt».
TEAR: 1976
(11) ABSTRACT: A tentative retereuce method is described for the
measurement of strontium-<;9 and strontium-90 in environmental waters.
Details of the method are presented in terms of its principle and
applicability, range and sensitivity, interferences, precision and
accuracy, apparatus, reagents, procedures, calibration, calculations
305
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HAZARDOUS WASTE MANAGEMENT!
and reporting. In the aethod, samples of environmental water sources
are collected, preserved with acid-strontium carrier, and analyzed for
strontium-89 and/or strontium-90. both types of strontium are separated
from the sample water by precipitating with stable strontium carrier as
carbonate. The strontium carbonate is dissolved; yttrium-90 is
separated and strontium is then reprecipitared as carDonate, filtered,
and counted for combined strontium-B9 and strontium-90 activity.
Yttrium-90 is allowed to grow in fro» strontiam-90 activity, ana
strontium carbonate is redissolved. Yttraum-90 is then separated
precipitated, and counted for strontium-90 determination. Strontium-89
activity is determined by the difference between total strontium-89 and
strontium-90 and separate strontmm-90 activities. Recoveries are
determined from added and found (recovered) strontium carrier. Counting
efficiencies are determined with prepared standard reference samples,
and results are reported in picocuries per liter.
(12) KEKBORDS: ANALYSIS; (JHEHiCAL; CLIMATE; IbOTOPE; HEASOREHENTS;
POLLUTION; RADIOACTIVE; KEFhRKNCK; SAMPLING BETHODS; SEPARATING;
WATER SAY
(15) ST1HS ACC.HO.: OOS35159
(18) DOC.CIT.: KPA Environmental Honitoring and support Lab.
Heasurement of strontium-69 and strontium-90 in environmental waters: a
tentative reference method. Las Vegas, MV, 0. S. Environmental
Protection Agency, Bar. 1976, 2b p.
(1) SIIRS ACC.MO.: 036090
(2) DOMESTIC: D (2) CATEGORY: 0» (2) SUbJ.Tlfl-E: S (10) PUB.
IJJAfi: 1976
(11) ABSTRACT: The importance of tritium as gas in the
contamination of plants and soils is examined. Lettuce plants were
grown in a mixture of peat and vermiculite and watered with a modified
hoaglands nutrient solution. Studies were conducted in plant growth
chambers, and tritium concentrations associated with organic
constituents of the lettuce plants were determined by oxidizing dry
plant material in a pressurized oxygen bomb and subsequently analyzing
the water of combustion. Tritium concentrations in leachate, transpired
water, water extracted from the plants, and the water of combustion
were analyzed using liquid scintillation techniques. Lettuce plants
fumigated with elemental tritium accumulated tritium in plant water as
well as in organic constituents. The conversion rate of elemental
tritium to tritiated water varied from 0. 5 nanocuries per minute per
pot at the start to 0. & nanocuries per minute per pot when the 24-day
exposure to an air concentration of S nanocuries per liter was
terminated. Based on the concentration of tritium in various plant
tissues, foliar absorption was postulated as the route of plant
contamination. Study data indicated that an enzymatically facilitated
conversion on the leal or soil surface was the probable mechanism.
(12) KEYWORDS: CATALYST; CONCEMTRATlUN; GASSBS; HAZARDOUS; LAND;
HEA.SUREBE8TS; MONITOR; ORGANIC; OXYGEN; POLLUTION; VEGETABLE;
VEGETATION; MATER
(15) STIHS ACC.NO.: OOS35135
(18) DOC.CIT.: HcParlane, J. C. Tritium accumulation in lettuce
fumigated with elemental tritium. Las Vegas, «V, U. S. Environmental
Protection Agency, Jan. 1976, 19 p.
(1) SHIRS ACC.IO.: 036069
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUbJ.TYPE: T (10) PUB.
IBM: 1975
(11) ABSTRACT: A neutron activation laboratory with computer
coupled equipment and procedures is described that was established to
analyze environmental trace materials. The capability of the laboratory
for environmental trace material analysis was demonstrated by analyzing
various materials, including quality control interlaboratory
comparisons. Samples ranged from sewage treatment plant sludge and
marine sediment to fresh water containing very low concentrations of
molybdenum and ore and fertilizer containing cadmium. It was concluded
that neutron activation analysis (NAA) is desirable for environmental
tracer experiments because it is sensitive and uses constituent tracer
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RADIOACTIVE WASTES
nuclides rather tcan introducing other tracers. Tiie total cost of
simple e^uipaent in the laboratory was about *40,000 (in 1972), plus
access to a time sharing computer system and nuclear reactor. A
comparison of analytical results indicated that either atomic
absorption or NAA can be used to analyze environmental trace materials,
although the ainiouJi size of saapj.es ditfered significantly for the two
methods. It was deaonstrated that automated environmental monitoring
with graphic display can be Carried out using hAA and, in addition to
its general usefulness as a sensitive method ior trace analysis, «AA
can be used as a reteree or eoaparifcon nethod.
(12) KEiHOHDS: ANALYSIS; LQfil'AHISON ; CGflpUTEK ; CONCKSTRAI'lON;
COSJfiOL; ECONOMICS; ilt'Uli'MEKr; hJJXAJ.; HGNiTOK; POLLUTION; PKOCESS;
SEWAGE; TOXIC; HATEtiWAY
(15) ST1HS ACC.tiO.: OOS35134
(IB) DOC.CIT.: Feidmaii, M. H. , L>. E. Cawineid, and K. V. tsyram.
Environmental trace materials; computer coupled radioactivation
analysis. Corvallis, ofi, U. S. Environs, en tal Protection Agency, Dec.
1975. 36 p.
(1) SHIRS ACC.NO.: 036011
(2) DOHESTIC: F (2) CA'IEGOhi: ua (2) SUuJ.l'yPE: S; T (10) i>OB.
1975
(11J ABSTRACT: An experiaentAl study of btrontiun i*0 soil content,
tests the effect of radioactive metals on 20-day old t»neat sprouts; it
de»onstrates that at a ai^h degree o± radioactive soil conta»ination,
with the increase of i>r 90 concent ration, increases tne accumulation of
Sr 90 in vegetation. Experiments Here carried out on two types ot soil:
sod—podzolic - with Ca content ot t>. a ailiiequiv per TOO tjraas of
soil, and chernozem - with ca content ot 26. t> aiiliejuiv per 100 grass
of soil. Sprouts were groan in weigtsing bottles containing 60 g ot
soil. Soil was netted with distillea water and Sr 90, in the form of Sr
C12 without a carrier, which then was added to acnieve gradual
concentrations of 10, 40, 400, dOO uaiiocurie per gram ot soil. Soil was
seasoned for 28 days whereupon ten *heat sprout grains were planted in
each bottle. The experiment was carried on/in a luminescent chamber for
20 days under a moisture ieyi«e siigatly lower than actual field
condi tions.
(12) KEXHOBDS: CHAMtiLii; CONC£N'PhAJ'lON; COMTAMiN ATb; LAND;
BADIOACTIVE; VEGETATION; WATEH
(1b) STIBS ACC.NO.: OOS3505b
(loj DOC.CIX.: ZuLareva, 1. F. ittect ox 90-Sh concentration in
soil on accumulation of radioactive strontium in wheat sprouts.
Vliyaniye kontsentratsii bO-SK v pochve na Koeiritsxenty naXopleniya
radiostrontsiya v prorostkaKn psnenit-jy. Agroxhiaiiya, 10:135-136, 1975.
(I) SW1ES ACC.HO.: 036019
{2J DUBESTIC: F (2) CATfcGOKY: 09 (2) SUbJ.TypK: T (10) PUB.
XKAR: 1975
(tl) ABSI'RACT: ireatment ot waste from atomic power plants,
exeaplified at the NovovoroneznsKiiya in Central European Russia, ana
Beloyarsxaya in the Oral region plants, has thus far been described as
satisfactory. The entire surrounding urea with a radius or 10-12 Km, is
subject to uninterrupted monitoring, ioiid waste products are stored in
largecapacity ferroconcrete bins if highly radioactive or are buried in
trencnes if less radioactive, fcnere nydrogeologicai conditions are not
favorable, specially-insulated tranches are provided to prevent any
washout of radioactive scatter. Solid waste witn a relatively low
radioactivity still presents a problem. Compression 01 inch waste
material is conteaplated.
(12) KEYWORDS: fcUhY; COflPACTION ; CONCitETi; GEOLOGIC; HOSITOH;
PLAHT-ISDOSTRIAL; POHfcR; RAitlOACTlVt; SJTOKAl,!.; 1'R K A T« ill T; X»ENCH; MATEB
(15) STIrtS ACC.No.: OOS35064
(18) DOC.CIT.: burnazyan, A. i. , Radiation safety in nuclear power
plant operations. Kadiatsionnaya bezopasnost pri eJtspluatatsii atomnykh
elektrostantsiy. Atomnaya Energiya, j«(3):167-172, Sep. 1975.
307
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HAZARDOUS WASTE MANAGEMENT
(1) SUBS ACC.NO.: 035861
(2) DOMESTIC: D (2) CAfEGOBT: (if (2) SOfaJ ,1X^£: G (10J PUB.
YEAR: 1475
(11) ABSTRACT: Present and future problems in the management of
nuclear wastes are considered. Sate operation of a nuclear reactor
should encompass the entire nucxear fuel cycle, including fuel supply,
reprocessing, and disposal of wastes. The residue from a ill tailings is
a einor but persistent aazard. Steps should be taxen tor proper
location and disposal of these wastes. Fuel storage space is cecoming a
pressing problem requiring immediate attention. Decommissioning of
facilities will become a problem in another 20 or 30 years. Three
stages are required: lock up with surveillance; conversion and
restricted site release; and unrestricted site release. Gas recovery
processes should be developed and used so that dangerous materials such
as krypton a5 and tritium don't escape into the atmosphere and
biosphere. The costs versus the benefits must be ascertained for
separating alpha bearing wastes from .tuels. Two methods of disposal
toat can be utilized in this century are disposal in the earth surface
and in geological formations, small countries should cooperate in
regional centers for fuel reprocessing and waste handling to cut
handling and operating costs, to reduce the numbers and sources of
radioactivity, and to reduce the risKs of accidents. Maturity of
nuclear energy is the ability to manage it wisely, saiely and in
cooperation.
(12) KEYWORDS: ACCIDENT; DISPOSAL; ECONOMIC^; FUEL; GASSES;
GEOLOGIC; HAZARDOUS; INTERNATIONAL; MANAGEMENT; PLANNING; PhOBLEHS;
RADIATION; RADIOACTIVE; REGIONAL; STGHAGE
(15) STIHS ACC.NO.: OOS349U6
(18) DOC.C1T.: Lennemanii. U. L. , H. K. Parker, and P. J. Jest.
Management of radioactive wastes. International Atomic Energy Bulletin,
11(41 :2-13, Aug. 1975.
(1) SHIRS ACC.NO.: 035740
(2) DOMESTIC: D (2) CATEGORY: 09 U) SOttJ.TXPE: T (.10) PUB.
IBAH; 1*75
(11) ABSTRACT: As nuclear fission increases as a source ot energy
over the next several decades the problems of treatment, separation,
shipment, and long teim disposal of radioisotopes will become more
acute. The management of these wastes and the technology being
developed to treat solid wastes* cuntaainated with radioactivity are
described, along with the techniques being considered for long term
storage and disposal. Projections of annual rates of generation and
accumulation of 10 categories of radioactive wastes are given. A
regulation proposed by the U. S. Atomic Energy Commission would
prohibit the further burial of commercial transuranium wastes in the
soil and would require that they 0e turned over to Federal custody. An
objective of the 0. S. Energy Research and Development Agency is to
improve the form and composition of waste materials to contribute to
economic and effective disposal. Solid contaminated wastes include
combustible wastes, liquid and sludye wastes, and non-combustible
wastes. Methods of treating combustible wastes include acid digestion,
controlled air incineration, pyrolysis, molten salt combustion,
fluidized bed combustion, aud cyclone incineration. Common techniques
for treating liquid and sluage wastes are batch and continuous process
phosphate treatment. Non-combui>tible wastes include many precious
metals and thus have a high recovery value. Methods of treatment
include saelting, treating cladding hulls before contact, and
contaminating cladding hulls. Disposing radioactive wastes safely can
be accomplished with existing analytical capabilities and technology.
(12) KEYWORDS: DISPOSAL; ECONOMICS; FEDERAL; HAZARDOUS; MANAGEMENT;
HETAL; NUM-FERRGUS; PROJECTION; RADIOACTIVE; RECLAMATION; REGULATIONS;
SLUDGE; SOLID; TREATMENT
(•»:>) STIMS ACC.NO.: OOS3U7b5
(18) DOC.C1T.: Wolfe, R. A. Problems and prospects in the
management of solid radioactive waste. The Journal of Knvironiental
Sciences, 18(4):9-15, July/Aug. 1»75.
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RADIOACTIVE WASTES
(1) SHIRS ACC.NO.: 035643
(2) DOMESTIC: D (2) CATiUiOfcl; Of U) SUBJ.TYPE: G (10) PUB.
IBAR: 1975
(11) ABSTRACT: Scientists at the fcnergy Research and Development
Administration are looking tor ways ot disposing of radioactive wastes
without creating hazards toe future generations. The most serious
concerns are the carcinogenic and mutagenic potential ot radioactive
substances. Inadequate storage or disposal could allow wastes to get
into the atmosphere. Up to now, most radioactive wastes were generated
by the nuclear weapons research program. The wastes generated by
commercially operated nuclear power plants are six ti»es core reactive
than the weaponry waste, tfhen tue fission products interfere with the
reaction, the contaminated fuel is removed fro* the reactor, the
reclaiming of uranium and plutonium Iron contaminated fuel has not been
done on a large scale. At least three elements of the nuclear waste
pose serious dangers: plutoniua 239; strontium 90; and cesium 137. the
carcinogenic plutonium lengthens the aazardous life ot the waste to a
quarter of a million years. The government is in the process of
solidifying its waste. Methods of temporarily storing the wastes were
developed by the Atlantic Bichfield Company. Deep salt beds have 0een
proposed for a long term disposal ot radioactive wastes. Geologic
changes might expose the sites but it would take longer for such
changes to occur than it takes even the longest lived wastes to decay.
The salt bed sites have run into some problems. Geological alternatives
include: seabed disposal; burial in granite rock below 3 to 5 thousand
feet; and disposal in the Antarctic ice sneet. A uranium mine in Gabon,
Africa, was the site of a natural nuclear reactor, two billion years
ago; only the cesium has migrated significantly. Whatever disposal
system is chosen there will always be the problem of human error.
(12) KEYWORDS: ANTARCTICA; DISPOSAL; ENKBGI; FUEL; GEOLOGIC;
HAZARDOUS; HEALTH; BIKE; OCEAM; PUBLIC UTILITY; fiADIUACTIVE;
RECLAMATION; SALT; SITES; STOWAGE
(IS) STIflS ACC.NO.: OOS34668
(1tt) DOC.CIT.: Gorman, J. Handeriug in the nuclear waste land. The
Sciences, 15(8):6-10, Nov. 1975.
(1) SHIRS ACC.KO.: 035634
(2) DOMESTIC: D (2) CATEGORY: 09 (2) SUBJ.TYPE: S (10) PUB.
IBAK: 1975
(11) ABSTRACT: A computer program was designed to conduct an
inventory of the Haxey Flats nuclear waste burial site. The total site
activity was estimated by adding activities by isotopes after decaying
the activity from date of burial to present date. Undated depositions
were considered buried on the closing date ot the pit in which they
were put. The activity of individual pits was determined at burial time
and at present time. Additions were also made witfi regard to total
isotope activities on the site and volumes of disposal by pit and by
site. Although an accurate evaluation of the error associated with the
statistics is impossible, tais method of recording tends to
systematically increase the recorded value against the actual activity
of a shipment.
(12) KETfcOBDS: bURX; COMPUTER; DISPOSAL; HAZAKDOUS; ISOTOPE;
MANAGEMENT; PBOGhABHiHG; KAlUOACTIVE; SURVEY
(15) STIHS ACC.NO.: OOS34679
(18) DOC.CIT.: Gat, 0. , J. i). Thomas, and 0. T. Clark. Maxey Plats
nuclear waste burial site-inventory. Transactions ot the American
Nuclear Society. 265-26t>, June 9-13, 1975.
(1) SHIRS ACC.NO.: 035619
(2) DOMESTIC: t (2) CATEGOBI: 09 (2) SUBJ.TYPE: T (10) PUB.
IEAB: 1975
(11) ABSTRACT: This patent provides a disposal device for ashes
generated during the incineration of radioactive wastes from nuclear
reactors, which will decrease the volume of tne ashes waile producing
safe and manageable solidified blocks. The wastes treated by this
process include such solid combustible wastes as ion exchange resins,
cellulose powders, and liquid wastes containing mostly sodium sulfate.
The incineration ashes and waste water are mixed and crushed in a
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HAZARDOUS WASTE MANAGEMENT
mixing chamber to form A slurry which is 70 to ao percent water by
weight. Liquid wastes are heated to boO C in the incinerator and are
dehydrated to a solid sodium sulfate. At a prescribed interval the
slurry enters the incinerator for a very short; period of tine. These
processes are repeated until the incinerator is filled witn alternate
layers of slurry and solid sodiu» suliate. This closed system type
disposal device can solidify the wastes without using solidifying
agents such as cement and asp bait, and the incinerator also serves as a
stock container. (Text in Japanese)
(12) KETUOBDS: ASH; HAZAHDOUS; HEAT; 1NC1NEKATION; JAPAN; PATENT;
RADIOACTIVE; SLOBBY; SOLID; SISTEB; TfiEATHEHT; HASTE BATEB
(15) STIHS ACC.NO.: 00334664
(18) DOC.CIT.: Oda, A. , H. Yusa, A. Odaoe, T. Inji, and K. Hakata.
Shokyaku bai no shori sochi. Disposal device tor incinerated ashes.
Japanese Patent Sho 50-27956 owned i>y K. K. Hitachi Seisakujo, Tokyo,
Japan. Issued Sept. 11, 1975.
(1) SHIES ACC.NO.: 0354 72
(2) DOMESTIC: D (2) CATEGOBY: 09 (2] SUBJ.TltPE: & (10) PUB.
TKAB: 1975
(11) ABSTRACT: A study oy the Environmental Protection Agency has
shown substantially elevated levels ot radioactive radon (radium
emanation) and its decay products in buildings constructed on reclaimed
phosphate mined lands in Polk County, Florida, continuous exposure tor
10 years could double the normal risk of lung cancer tor people living
in the buildings. Uranium concentrations in Florida pnosphate rocks are
generally 100 to 150 parts per million, while most United States soils
contain 0. 5 to 10 parts per Billion. Usually tnese phospaate deposits
lie several feet beneath an overburden of soil, and rock which absorbs
•ost of the radiation. Bemoval of this layer during mining allots
increased amounts of radiation to be released. The Occupational Safety
and Health Administration has proposed the reduction of permissible
employee exposure limit to lead from the present limit of 200
micro grams lead per cu m of air to 100 •icrograns per cu m. It has also
proposed a maximum blood lead level of to micrograms per 100 y of
blood. Lead industry officials immediately took issue with the
standards. Even during a time of high employment and rising fuel costs
the public does not want to cut back, on environmental programs. This is
the conclusion of a June 1975 survey i;y the Opinion Research
Corporation. Four mining companies are planning to use sewer effluent
water for their ore processing operation. Ose of the treated water
would help stretch underground reserves in tne area, The water table is
going down each year Baking pumpiug operatiohs expensive. It is
estimated that the mines may buy as much as 25 Billion of the 33
million gal per day generated by the sewage treatment plant.
(12) KEYWORDS: ECONOMICS; EFFLUENT; EMVIBOMHEDT; EPA; HEALTH; NINE;
HON-FBRHOOS; PEBSOMNEL; PHOSPhATE; BADIOACT1VE; SEWAGE; STANDARD;
SURVEY; TOXIC; TRBATHENT
(15) STIMS ACC.NO.: OOS34517
(16) DOC.CIT.: Alexander, C. Emphasizing environment. Mining
Bngineenng. 27(11) :59, Nov. 1975.
(1) SHIBS ACC.NO.:
(2) DOHESTIC: F (2) (.ATlniOfiY: 09 (2) SU6J.TYPE: S (10) PU£i.
SiAB: 1975
(11) ABSTRACT: The problem of subsurface, radioactive-contaminant
transfer is investigated through the development of a two-dimensional
lodel which considers the simultaneous flow ol water and mass. 1 a
addition to convection and dispersion, the model treats radioactive
decay and cation exchange which are two ot the sost important
attentuatiou processes. Tne influence of factors, unicn control the
transport processes subsutidce contaminant distributions, is
demonstrated through the siauiation and analysis of a series 01
hypothetical cases. Physical transport processes, hydraulic
conductivity, porous medium dispersivity and the location of the
contaminant intlow zone are considered to be tne controlling parameters
for the physical transport processes. The attenuation processes art
controlled by the radioactive Hair-life, selectivity coef ticient.s,
310
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RADIOACTIVE WASTES
cation-exchange capacity, ion charge, and weathering rate. The maximum
extent of subsurface contamination m all cases is determined by tne
physical transport processes. The complexity of the transport process
suggests that evaluations or jite behavior which are based on rigid
guidelines are inadequate tor siting and designing waste management
sites and for insuring the safety or water supplies.
(12) KEYWORDS: BIBLIOGIUPHY; DECOMPOSE; DESIGN; DISPOSAL;
BAZAfittOUS; HYDRAULIC; HANAGJiHilNI; POLLUTION; PROCESS; S flDIO/vcTIV t,;
EESEAHCH; SAFETY; SITES; TtfANSPOKT; HATtB
(15) SUMS ACC.HO.: OOS34457
(18) DOC.CIl.: Schwartz, *'. H. On radioactive waste management: ait
analysis of the parameters controlling subsurface contaainant transfer.
Jcutnal of Hydrology, 27 (1975) :5 1-7 1, 1975.
(t) SHIRS ACC.NO.: 034641
(2) DOflESTIC: P (2} CATEGORY: 09 (2) SOBJ.TYH.: X (10) i>UB.
IBA8: 1975
(11) ABSTRACT: This work is a literature survey ot selected
articles published between 19t>9 and 1974 dealing with the use ot
sorDents in the purification of low-and medium-level radioactive
waters. It also surveys selected work in the synthesis and laboracory
testing of new sorbents. The ten sorDents, in this review refers to
the substances in which there is pronounced accumulation of
microconstituents fro* solutions and which are not components of living
organisms. Apart from a few exceptions, tne review does not deal with
sorbents prepared either from costly or from toxic elements. Nor does
the review cover the use of ion-exchange membranes ana other types of
membranes for the purpose mentioned ot on sorbents of cranium and its
compounds. Under these restrictions, then, the following elements are
not reviewed: vanadiam; niooiun; tantalum; chroniun; molybdenum;
tungsten; cobalt; nickel; silver; gold; boron; gallium; beryllium;
cadmium; mercury; and arsenic. The review ties up witn two manuals
published by the International Atomic Energy Agency iu Vienna. Taey are
"operation and Control of Ion-exchange Processes for Treatment of
Radioactive tfastes" and "Use of Local Minerals in the 1'reatBent of
Radioactive Hastes. *
(t2) KEYWORDS: blBLlOGSAPHY; LA'1'A; LITERATOhE; KJfalFll-Al'lOIJ;
RADIOACTIVE; SORvfiY; WAIEk
(15) ST1BS ACC.SO.: 00333665
(t8) DOC.CIT.: berate, L. , Euher, and H. Harhol. i»rbents for the
purification of low-and medium-level radioactive waters. Keviev of
developments, 19t>J-197U. Atomic fcnergy Review, 13 (2) : J2b-3b6, June 1975.
(t) StoJRS ACC.MO.: Q3H212
(2) DOMESTIC: F (2) CATEGOfcY: 09 (2) oUbJ.TitPJi: T (1U) PUB.
YEAH: 1975
(11) ABSTRACT: the researcners give an account ot the present
situation in studies of the extraterrestrial msposai oi radioactive
wastes in all aspects including technical ana economic feasibility . Horizawu. Hosnasei haiicibutsu no
uchu shoiiuu. Extraterrestrial disposal of radioactive wastes.
Senshiryoku Kogyo, 21 (3):Jl-«1, Bar. 1975.
311
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HAZARDOUS WASTE MANAGEMENT
(1) SMIRb ACC.dO.: 034131
(2) DOMESTIC: F (2) CATBGOB5T: 09 (2) SUBJ.TYPi: T (10) PUB.
XBAR; 1*75
111) ABSTRACT: Jfhis article discusses tne long tera hazards
involved in the management of nuclear wastes. Kuratoa's Joint Research
Centre at Ispra, Italy, is in ves lighting the profii««s involved in the
separation of actinides, whica are the «ost long lasting radioactive
isotopes produced in nuclear power stations, from otner radioactive
wastes and has evaluated the .benefits that chemical separation of the
actinides would entail for radioactive waste management. 1'hese
investigations indicate that the hazards of radioactive waste
management could be reduced by a i actor of between 1,000 and 10,000
turough the decontamination ot the low level, snort-lived isotopes.
Different techniques ior separating actinides fro» ni^h activity waste
would allow for various levels 01 decontamination. However., even if the
actinides can tie separated from tue reprocessed nuclear fuel, the
methods ior the safe disposal of the separated actinides and the amount
and quality of th« additional wastes generated by the separation
process will need to tie examined ana evaluated.
(12) KEYWORDS: UENEflT; DISPOSAL; FUEL; hAZAHUOUS; INVESTIGATION;
ISOTOPE; MANAGEMENT; PLANT-IKDUSriilAL; PO«EB; PaOi»L£Bi; RADIOACTIVE;
SEPARATING
(15) Si-IMS ACC.NO.: 00aj317i>
lib) i.OC.CIT.: Nuclear vaste: lon>j term hazards. Ken scientist,
67(iJ57):yi, Juxy 10, 1975.
(1) SW1RS ACC.HO.: U34006
(2) 00HEST1C: P (2) CA'fEGOhJ: 0V U} iiUBJ.rYPE: G (10) PUh.
YBAK: 1975
(11) AbSTRACT: A reiote control nuiiature field car, developed as
part of a safety device project sponsored by the Bonn Ministry of
Research and Technology at Karlsruhe Nuclear Research Center, West
Germany, can handle and transport nuclear fuel and wai.te saiely.
Equipped with a yeiyer counter, temperature sensors and stereo
microphones, the car homes in on its target, moves its ar» into
position and analyzes its target with an array of spotlight, stereo and
closed-circuit TV caneras and aerials. The equipment is only J. B8 »
long and can easily Dt; shipped or flown by helicopter to toe .location
where its services would be required.
(12) RECORDS: isQDIPflEMT; HAZABUOUS ; nOdll'Oh; RAU10ACXI v£;
TBAUSPOhT
(15) STiflS ACC.NO.: UOS33050
(1bj DOC.C1T.: Mews in i,net . South African Mining and Engineering
Journal, 68 (*» 102) :97, Mar. 1975.
(11 ShlRb ACC.NO.: 0334-*!
(2) DOMESTIC: D (2) CATBGGhl: 09 (2} SUaj.TYPE: G (10) PUB.
XEAR: 1975
(11) ABSTRACT: A new regulatory guide is presentee, for leakage
tests on packages for snij-nent of radioactive materials. The guide is
in series and serves to moke avaij.aDlt? to the public aethods accpetable
to the National Kegulatory staff 01 xapleientiug specific parts of the
Commission «s regulations and to delineate tecuniques used by the staff
in evaluating specitic problens or postulated accidents. It also
provides guidance to applicants on inioriation needed uy the statt in
its review of applications tor peri^ts and licences.
(12) KEYKORDb: KlSPOSAt ; J'KDchiL; GOViRNMh«r; HAb/iRDOUS; I'UjsLIC;
RAD10AC11VE; REGULATIONS
(15) ST1W5 ACC.NO.: OOSJ246!)
(18) ixjc.cir.: Nuceidr reyuldtoiy commission: leaxaye tests.
Federal Register, 40 (11 7) :2564/, June IV,
(1) Si«Ifii> ACC.NO.:
(2) IJOflEbl'IC: F (2)
CATEGORY: 09 (2)
.T5( i-L: S (10) PUB.
(11) AtiSi'SACT:
important tnai.
yuestio.i: Is power from nuclear sources nore
engendered by thu sanie nuclear sources? Plutonium,
312
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RADIOACTIVE WASTES
the »ost hazardous factor iu th« auciear scheme, can oe transmitted
into the environment during by-product disposal which takes place in
the ocean, or toy disruption to the storage areas of high activity
wastes. Also radiation danger to workers in plutonj.ua fabrication
plants is a big problem. Lack, of direct data in the area of
radiological protection of personnel exposed tx> plutonium adds to the
problem of control exposure. Time is a factor in the assessment of
plutonian and whether its advantages are greater than its risks.
(12) KEYWORDS: DISPOSAL; ENVIUONHtUT; HA2.AKDOUS; IE8SGNNKL;
RADIOACTIVE; SAFETY; STORAGE
(15) STIMS ACC.NO.; OOS324S3
(18) DOC.C1T.: Plutonium-the risks TS. the benefits. Laboratory
Practice, 10(4) :47, Jan. 1975.
(1) SHIRS ACC.NO.: 033364
(2) DOBESTIC: F (2) CATEtiOKI: (iy {2} SOBJ.TYtE: T (10) PUB.
YBAHt 1975
(11) ABSTRACT: In the highly radioactive wastes arising by fluoride
processing of nuclear fuel troi fast reactors, most of the fission
products are adsorbed on granulated alumina. With the planned operation
of nuclear establishments in Czecnoslovakia, the production of
contaminated aluminum hydroxide should attain roughly 10 tons annually
in the 19BO's and gore than 200 tons by the end of the century. It is
necessary to solve the probien of disposal of such large quantities of
dangerous materials in the densely populated country. Into basalt,
which has already been proved as a suitable fixation medium for liguid
radioactive waste, it is possible to fuse further 30 percent aluminum
hydroxide without affecting negatively its properties. Basalt from the
Slapany locality has been proved to be a suitable fixation »eaiu» for
fast reactor wastes. During the heat treatment process it is possible
to o»it the recrystallization stage, thus rendering tne process
economically sore advantageous. (Teit in Czech)
(12) KEYWORDS: ALUMINUM; CHKH1CAL; CZECHOSLOVAKIA; DISPOSAL;
ISOTOPE; PH; PROCESS; RADIOACTIVE
(15) STIMS ACC.SO.: OOS32408
(18) DOC.C1T.: Ralkova, J „ , J. Pribyl. Prispevek k likvidaci
radioaXtivnich odpadu z rychlych reaktocu. A contribution to the
disposal of radioactive waste fro* fast reactors. CesJcoslovenska
Afcadeaie Ved 19(1): 69-75, 1975.
(t) SBIRS ACC.NO.:
(2) DOMESTIC: F (2) CATKGGhX: 0* (2) SUbJ.TItK: S; T (10) PUB.
YEAS: 197b
(11) ABSTRACT: Nuclear yroceiisin^ pxantii ttpply the Puirex process,
or variations ot it, almost ex.ciusive.i-y for extractive separation and
decontamination of uranium, neptunium, and plutoniua irom each otner
and from inpurities. As an exLractant, vri-n-butyl phosphate or TbP,
which is usually dilutee with saturated axiphatic hyarocaroons, such as
n-dodecane or refined kerosenes, is ui;ea. In the furex process, the TBP
as veil as the dilutent, and degraded cy radiation ana leaciive
chemicals. Degradation of the extractant phase causes a series ot
unfavorable effects on the extraction process and equipment operation,
such as loss of uranium and plutonium to waste streams and poor
separation of the solvent phase, ana the formation ana deposition of
solids. Currently used processes to minimize these disadvantages are
considered, however, for the most part, they are not satisfactory.
However, a new process aas iieeu developed for safe anu economic
treatment and disposal of spent TaP-kerosene mixtures which is tree of
tne disadvantages of the currently used treatment techniques. Tnis
process has been designated the Eurocnenic organic waste treatment
process, abbreviated the Eurowatt process. A aetaileu description of
tae process is contained iu this paper. Althou^a the process wau
313
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HAZARDOUS WASTE MANAGEMENT
developed specifically for tne treatment of spent TbP-kerosene
Mixtures, it is applicable to other solvent types also.
(12) KEYWORDS: AMALXSIS; CHEMICAL; CONVERT; DESItM; DISPOSAL;
EBEBSSf; IHDUSTRJ; LIQUID; PROCESS; hADIOACTIVi,; RKSEAKCh; SOLID;
SOLVENT; TREATMENT
(15) STIHS ACC.NO.; OOS31539
(t8J DOC.CIT.: Salomon, L. , h. Eschrich, and L. Humblet. treatment
and disposal of tributyl phosphate-kerosene waste by the Eurowatt
process. The American Nuclear society Transactions, 29(1-820):<»63-665,
1975.
(1) SHIRS ACC.so.: 03247tt
(2) DOMESTIC: D (2) CATEtiOhX: 09 (2) i>OBJ.TJ(PE: S; X [10) PUB.
YEAfii 1975
(11) ABSTRACT: Most of the high-level radioactive waste at the
Idaho National Engineering Laboratory is generated during the
reprocessing of spent nuclear fuel at the Idano Chemical
Processing-Plant. The fuel coaes from nuclear reactors that use. highly
enriched uraniun-235 fuel. Host of the high-level radioactive waste is
first-cycle raffinate from solvent extraction ot dissolved fuel
solutions. This waste is self-heating in botn the liquid and solid
foras. Management of these trastes is perfumed in accordance with the
latest requirements and regulations tor such waste. Liquid Haste is
stored safely in doubly contained tanks made of steel. The liquid waste
is calcined to a solid and stored safely in underground bins. The
calcine can be treated or left untreated in anticipation of ultimate
storage. Fluidized bed calcination has been applied to aany types of
high—level radioactive wastes. The environmental impact of the wastes
at the Idaho chemical Processing Plant has been negligible and should
continue to be so.
(12) KEXUORDS: CONTA1NEB; COKVEMI; DESIGN; DISPOSAL; EHV1BOHMENT;
FACILITY; FLUIDIZED BED; FUEL; Ii;AHO; LIQUID; MAHA6KHEDT; RADIOACTIVE;
SITES; SOLID; STORAGE
(15) STIfIS ACC.NO.: OOS315^
(IB) DOC.CIT.: Slansky, G. C. H. Kadioactive waste management.
Chemtech, 160-164, Mar. 1975.
(.1) SMIRS ACC.BO.: 032472
(2) DOMESTIC: D (2) CAKCOH*: OS (2) SOBJ.TIPE: S; T (10) POB.
YEAfi: 1975
(11) ABSTRACT: The reprocessing of irradiated fuels produces liquid
•ediun level wastes. Since 1V66 sucb wastes have Been stored on the
Eurocnemic site in belgiun in uncollea steel tanks. Before transporting
these wastes to an interim storage facility, it is necessary to convert
them to a water-insoiuble, solid form. This is done in a two-step
process: chemical pretreataent, to insoiubilize the radionaclides to
eliminate corrosion risks and uncontrollable thermal reactions; and,
homogeneous incorporation of the slurry resulting from the chemical
pretreataent into bituaen aiotg with the simultaneous evaporation ot
vater to obtain solid bitiuicn waste, i'his product is poured into dru*s
suited for interim storage ana tinal disposal, rhts report described
the bituainization and storage instaxiations, evaluates tne hazards
involved, and analyzes the aaiety aspects ot the operations with regard
to public nealtn and environmental considerations.
112} KErrfORBS: toELGlUfi; CONTAINER; CONVERT; DISPOSAL; EMVIRONHEHf;
FACXLlfi; LIQUID; PBOCESS; KADIOACTIVi,; SAFETI; SITES; SOLID; STOHAGE;
IttASSPOKT
STIflS ACC.NO.: OOSjIblb
DOC.CIT.: Medium level waste bituminization plant and
engineered storage facility at Eurocrienic. Tne American Nuciear society
Transactions, 20 (1-c20) :o5o-661, 1V75.
(1) SB1HS ACC.NO.: 032471
(2) DOMESTIC: D (2) CA T£GOi< X: Oy (Z) SUfcJ.l'KPE: S; r (10) POM.
XEAR: 1975
(11) ABSTRACT: All liquid radioactive wastes »ust be solidified in
order co prevent the release of radionuclides to the environment. There
314
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RADIOACTIVE WASTES
are two industrial processes xor the solidification o± low and nediun
level liquid wastes: uituaenization and cementation. The disadvantages
to the latter incluae: formation of heterogeneous blocus; incoaplete
setting of ceient with sone evaporation concentrates; poor resistance
of solidified wastes to climatic variations aad shocks, high leaching
rate, ana increased voluae after pacKing. Mainly tor these reasons,
France uses nostiy bitaniuination. i'he uituninization process consists
of thoroughly aixing these cold liyuid wastes with hot Ditu»ea fed at
its pumping temperature or with cola tiituainous eaulsion, and perrectly
dehydrating the coated product ty proyressiveiy heating tue soluble and
iusoluble salts and Dituaen. These two processes are carried out
siaultaneousiy in a continuous operating evaporator. This paper
discussed the saiety proclens associated with radioactive wastes
solidified oy bitumen.
(12) KEYWORDS: ANALYSIS; COHPAfiiSGN; UONCjiEl'E; CuhTAINEh; COHVBftT;
DISPOSAL; ENVIKOHMENr; FKANUi; LIQUID; WUbLfcflS; i-BOCESS; RADIOACTIVE;
SAFETY; SOLID; STORAGE
(IS) STIMS ACC.HO.: OOSJlbli
C\a) DOC.CII.: Lefiilatre, G. , and j. Leconnetabie. bituniiiization
of radioactive wastes: sarety prod tuts and applicatiou tields. The
American Nuclear Society Transactions, 20 (1-620) :fabV-65tj,
(1) i«lRJ> ACC.jlO.: OJ24/0
(2) OOMBST1C: D (2) CATEiiUHX: 0» (2) SUfcJ.TYPE: S; T (10) It-Da.
YEAR: 19V5
(11J A&STSACt: It is iairly comoiou practice to convert liquid and
slurry toras of radioactive waste to ^oiids betore storage or
transport. Kcouonical operation ot centralized facilities requires
relatively high throughputs of radioactive material, owing to this
factor and the increased dirticulties ol transport-ing liquid and slurry
radioactive wastes on public roadways, a Bobile waste solidification
systea is proposed, the design ot sucn a proposed unit is described.
The advantages oi such a unit include: the resulting transportation of
only solid wastes; the specific invtstaect costs to reactor owners are
lower for the lower throughputs because no costs for location,
building, and infrastructure are required; one oobile unit can service
light-water reactors, nowever, it could also
treat ion exchange material.
(12) KEYWORDS: COfcrAISEa; CONVKhT; JLSI«B; ECOHOMiCb; EglllPrtEMT;
FACILITY; I0» £XCfcA«G2; LIQUID; MoV*i>LE; PfiOCKiij; fiaiiiuACriVi.1; SLUSHY;
SOLID; STORAGK; TRAMSfOhT
ST1MS ACC.BO.: OOSJ1S1U
UOC.CIT.: Shank, E. ft. uituminizatiou of liguid and slurry
radioactive waste in a vouile unit. The American HUclear society
Transactions, 20 I1-b2o) :6o1-bo2, I97b.
(1) SWIRS ACC.SO.: 0324bi*
(2) iiOflESriC: D (2) CATEGOKX: df (2) SubJ.XYl'E: S; T (10) PUB.
YE Ah: 1*7!>
(11) ABSTRACT: I'he ofclsenbeix Lompuny of Jerffl image:
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HAZARDOUS WASTE MANAGEMENT
advantages of usiug this process tor tn<; uoiidif icatiou 01 liquid high
level radioactive wastes.
(12) KEYWORDS: AHALiSIS; CHEMICAL; t_OdVt«l'; GLASS; Li^UiU; Bti'AL;
PHOSPHATt; PROBLtas; PrtOCESb; fcAwIOAC'i'I V£; RESEAWCH; SLUhRY; SOLID;
TB EAT BEST
(15) STiaS ACC.NO.: 005315 lj
(1b) DGC.CII. : Heimeri, H . * new method ror the fixation of high
level radioactive vaster. Toe American nuclear Society transactions,
20 (1-820) :669-o71, 1975.
(1) SHiHi> ACC.NO.:
(2) DOMESTIC: D (2) UUEGOkY: 0* (t) SUbJ.TYPE: S; I (10) PUB.
IBAK: 1975
(11) ABSTRACT: All liyht-*ater reactors have radioactive or f gas
effluents which aust ue treated to reduce the radioactivity prior to
release to the environment. Good operating practice as wei.1 as
governmental regulations mandate uceaLnent systems. Basically, there
are two nays of dealing witn radioactive wastes; temporary storage to
permit vost of tlie short-lived uucliaes to decay natiuaily, and removal
for peraanent storage. Treataent ;;ysteas lor the ladioactive orcgasses
generated in pressurized-»ater reactors and i)aning-«ater reactors are
described, with the commonly eapioyed reduction processes, to «eet
increasingly stringent requirements ror gaseous radioactive emissions.
Although the naiu purpose ol these systems is to reduce radioactivity,
they are also designed to optimize reliaflilit y, laintuicauility ,
safety, and cost.
(t2) KEYWORDS: ANALYSIS; DESIGN; fcN VlfiOKfliMf; EuUiP«£Nr; GA.SS£S;
PLANT-IHi;USXElAL; PO« EB ; KAUlOACTIV i; fifcDOC'X'lUJ* ; KEGUiJV f IONS; SAFilTY;
STOhAGE; SSfSTEB; TBEATMLNI
(tf>) M'lHS ACC.NO.: OOS31504
(lo) DOC.CI1.: Stewart, J- i.. , aud H. A. Knandar. Radwaste
reduction techniques tor LUK gaseous effluents. Tne American Nuclear
Society transactions, 20 (1-b20) :b49-6^4 , 1975.
(1) SHIMS ACC.NO.: 0324 59
(2) OOBESTIC: D (2) CATEGOHS: o« (2) SOBJ.l'YJ^Ji: b; T ( lU) fOB.
TEAK: 1975
(11) AUSl'RACT: hith the expansion and developnent of nuclear
programs, it is necessary to also develop adequate, reliable systems
for dealing wita the large aaountii ot radioactive wastes that are
produced. Radioactive waste management practices tor liquid, solid and
gaseous Hastes generated at pressurized-vater reactors are discussed
with frequent reference to operating experience at existing facilities.
Unfortunately, in many instances, too little attention is given to
unsatisfactory experiences. It is stressed that waste treatnent systems
• ust lie viewed as a whole. The Various i unctions of such treatment
stations, being strongly interconnected and haviny numerous
interactions, require that ttie different i,arts of tne system ana their
ancillaries be adapted and coordinated to each otner to achieve
operable and economical plants.
(12) KEY*ORDS: ANALYSIS; t«i.8Gi; i.«VIttONB£fcX; FAClLlii; GASSSb;
LIQUID; SANAGEHjiNT; i-LA*T-lNDO blitiAi-; POiifcR; PKUBLEHS; KAUIUACTlVi, ;
SAPEH; SOLID; SYSTbfl; TRtATHtNT
(15) STIHS ACC.NO.: OOSJ150J
(18) DOC.CIT.: lletgan, L. , G. Gallois, J. Heiitrez, and J. i.torrer.
Trends for PWfi radwaste treatneat stations a basis of present
experience. The American Nuclear iocxtty Transactions,
(1) SWISS ACC.NO. : 032407
(2) DOMESTIC: f (2) CAT hiGOblf; 09 (2) SUBJ.TYPE: G (10) ±>Ub.
YlAfi: 1975
(11) ABSlRAcT: bLitisn Nuclear fuels Ltd. is currently storing its
tulky radioactive wastes as liguius 111 stainless stttl tan*s surrounded
ty tiiicx concrtte shielding. However, as the expected use 01 nuclear
fuels will increase greatly, new Methods are. bein>j sought. Storage ox,
the wastes as solids would nave tne advantages o± ^iinpliried
surveillance and the feasibility ot transporting the containers iron
316
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RADIOACTIVE WASTES
cue site to an ether it deeaed necessary. A new process, a form of
nitrification, has been proved ou au experimental scale, and a
full-scale demonstration plant is planned for completion tiy the
iid-1980's.
(12) KEXWOHDS; CHEMICAL; CONTAINED; FACILITY; FUEL; tiaEAT
HAZARDOUS; LIO.UIC; flOBITGB; i-LAWNiNG; PROCESS; feAUIOACTlWfi; SITriS;
SOLID; STORAGE; THAMSPORT
(15) suns ACC.NO. : OOS31451
(18) DOC.CI'I.; Beatson, C. ttuclear wastes stored as solids. The
iugineer, 7, Feb. 6, 1975.
(1) SHIRS ACC.tfO.: 032123
(2) DOMESTIC: D (2) CATEGORY; 0* (2) SOBJ-iTPE: S; X (10)
XEAB: 1975
(11) AbSTHACT: Permanent disposal of nuclear wastes, is a proclem
with no immediate feasible solution, i'he United States has already
produced radioactive wastes taat will reaain axghly toxic foe up to
250,000 years; and there are no permanent sites available foe disposal.
Tie salt, beas in Bexico which have i*een stable lor ^50 million years
have been considered as possible sites, out taey will not be ready tor
about 20 years. Meanwhile, temporary sites are ueiny explored, one such
proposal is to solidify the toxic wastes and seal then iu 10 It high,
2-ton steel canisters and then eaued them in concrete casks. The 70 -ton
casks would then be erected on a barren plot and stored on the surface.
This would leave thei vulnerable to aircraft attack. Burying thea oelow
the surface would require a »ore complicated cooling system. Scneses
that have already been rejected are rocxeting the wastes out into
space, letting thea aelt into the poi^r ice caps, or Keeping then
•oving in railroad cars. The Energy Research and ue?eiopaent
Administration estimate a that by 2000, 60 million gal of wastes will be
produced. Permanent disposal needs will not i>e critical until then and
hopefully, new techniques will oe available by then.
(12) KEIMOHDS: BUB!; CO NT A IN £H; DISPOSAL; GUV EftMHtNT ; UA^AfiDOUS;
LIQUID; HEX1CO; fiADIOACTIVE; SAIL HAOL; RAILHOAD CAH; SALT; SiTKS;
SOLID; SPACE CRAFT; STORAGE; TOIIC; OS
(15) SIIHS ACC.HO.: OOS31167
(16) DOC. C IT-: ihe deadly dilesaa ol nuclear wastes. Knvirounent,
70-71, Har. 3, 1*75.
(1) 3WIRS ACC.NO.:
(2) DOMESTIC: F (2) CATt-JdhY: 09 (i) SUBJ.TYPE: T (10) FOB.
TEAK: 1975
(11) ABSTRACT: This paper was presented at the tirst European
Nuclear Conference held 01. April 21 to 25, 1975, in Paris, France. It
deals with the nature of radioactive wastes generated in the various
sectors of the nuclear tut.l cycle and their management. The wastes may
be characterized as mill- tailings, low level liquid and ^olid wastes,
qaseous wastes, and wastes containing plutonium and other actinides.
Management technologies lor these wastes are developed. Additional
technologies that currently receive attention are: 1) perpetual
isolation within tne earth until tiit process of natural decay converts
the radionuclides to a stable state; 2) removal rrom the earth by
prelection into space, and 3) transmutation or the long-lived
radionuclides to stable or short-lived radionuclides. Presently
acceptable, but rot implemented methods ol radioactive waste management
cr disposal metnoJs involve uotii engineered storage and geolocjij
storage of solidified hiqJi- level wastes. There is also very little
cooperation between nations in the implementation o£ radioactive waste
management practices. Radioactive waste management should be viewed as
a local, regional, and gloual proolem both in the short-run and
lonq-run terms.
(12) KEYHOHDS: DISt'GijAL; ECONOMICS; EUROPE; FRANCE; GOVtrtNMfcM;
HAZARDOUS; INTERNATIONAL; AMi aGiirit NT ; PROCESS; RADIO ACTIVE; HEGIUNAL;
RESEARCH
(15) STIMS ACC.NO.: OOSJ1102
(18) DOC.CI1.: Lenneiuarm, H. L. , H. E. Parker, and P. J. hest.
Hanageoent of radioactive wuste^. i he American Nuclt'ar Society
Transactions, 20 (1d2 3) : 6y 0, 1J75.
317
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image:
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Appendix A
ABBREVIATIONS
Administration
Agrarie
Agricultural
Agriculture
Amer ica(n)
Annals, Annali, Annales
Applied
Archiv (e, es)
Association (cion)
Australasian
Berichte
British
Buildings
Bulletin
Canada(ian)
Chemical, Chemistry
Company
Communication(s)
Control
Conservation Development
Deutschen
Corporation
Department
Division
Energy
Engineer(s)
Engineering
Environment
Environmental
Experimental
Government
Highway(s)
Incorporated
Indian
Industrial
Industry
Institute
Institution
International
Izvestiya
Japan
Japanese
Journal
Laboratory
Limited
Management
Manufacture(r)
Materials
Metallurgical, Metallurgy
Microbiology (leal, ia)
Mining
National
New
Number
Organization
Packaging
Pollution
Proceedings
Production
Admin
Agra
Agr ic
Agri
Amer
Ann
Appl
Arch
Assoc
Austral
Ber
Brit
Bldg(s)
Bull
Can
Chem
Co
Comm
Contr
Conser Devt
Deutsch
Corp
Dept
Div
Ener
Engr (s)
Engring
Env
Environ
Eptl
Govt
Hgwy(s)
Inc
Indn
Indus
Ind
Inst
Instit
Inter
Izv
Jpn
Jpnse
J
Lab
Ltd
Mgmt
Manuf
Mater
Metall
Micro
Mng
Natl
N
No.
Org
Pkg
Poll
Proc
Prod
319
image:
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HAZARDOUS WASTE MANAGEMENT
Professional Prof
Publication(s) Pub(s)
Reclamation Reclam
Report(s) Rpt(s)
Research Rsch
Resource Res
Review(s), Revue, Revista Rev
Service(s) Svc(s)
Science(s) Sci
South S
Technological Technol
Technology, Technische, Techn- Tech
ica , etc.
Toxicology Toxicol
Transactions Trans
Treatment Trtmt
University and variations Univ
United States U.S.
Water Wtr
Wissenschaftlichen Wissen
Zeitschrift Zeit
Zentrallblatt Zent
Zhurnal Zh
320
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Appendix B
QUANTITATIVE MEASUREMENTS
acre (acre) millimeter (mm)
acre-foot (acre-ft) mile (mile)
centimeter (cm) newton (N)
cubic centimeter (cu cm) one kilogram force (kgf)
cubic foot (cu ft) one pound force (Ibf)
cubic inch (cu in) pascal (Pa)
cubic meter (cu m) pound (Ib)
cubic meters per minute pounds per square foot (psf)
(cu m/min)
pounds per square inch (psi)
cubic yard (cu yd)
square centimeter (sq cm)
ft (ft)
square foot (sq ft)
gallon (gal)
square inch (sq in)
gallons per minute
(gal/min) square kilometer (sq km)
hectare (ha) square meter (sq m)
inch (in) square mile (sq mile)
kilogram (kg) square yard (sq yd)
meter (m) ton (ton)
yard (yd)
Months of the Year
Jan.
Feb.
Mar.
Apr.
May
June
July
Aug .
Sep .
Oct.
Nov.
Dec .
321
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Appendix C
LANGUAGE CODES
Language
Code
Mixed
Afrikaans
Albanian
Amharic
Arabic
Armenian
Belorussian
(White Russian)
Bulgarian
Burmese
Cambodian
Cantonese
Chinese
Croatian
Czech
Danish
Dutch
English
Estonian
Finnish
Flemish
French
Georgian
German
Greek
Gujarat!
Hebrew
Hindi
Hindustani
Hungarian (Magyar)
Icelandic
Indonesian
Italian
Japanese
Javanese
Kashmiri
Khmer
Kirundi
Korean
Latin
Latvian
Lithuanian
AA
AF
AL
AR
AR
AE
BE
BU
BR
CA
CH
CH
CR
CZ
DA
DU
EN
ES
FI
FL
FR
GE
GM
GR
GU
HE
HI
HI
HU
1C
MI
IT
JA
JV
KA
CA
KI
KO
LA
LN
LI
Language
Llngala
Macedonian
Malayan
Malayalam
Malay-Indonesian
Malagasy
Maltese
Mandarin
Marachi
Mongolian
Nepali
Ngala
Norwegian
Papuan
Persian
Polish
Portugese
Punjabi
Pustu
Romanian
Russian
Rwanda
Servian
Sinhalese
Slovak
Slovene
Somali
Spanish
Swahili
Swedish
Tagalog
Tamil
Telugu
Thai
Tibetan
Turkish
Ukrainian
Urdu
Vietnamese
White Russian
Yiddish
Code
NG
MC
ML
MA
MI
MS
MT
CH
MR
MO
HE
NG
NO
PA
PE
PO
PR
PU
PS
RO
RU
RW
SE
SI
SL
SV
SO
SP
SW
SD
TA
TM
TE
TH
TI
TU
UK
UR
VI
BE
YI
322
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Appendix D
HIERARCHIC TERMS
1AC ACCIDENT
(See also PETROCHEMICALS)
1AG AGRICULTURAL WASTES
(See also ANIMALS, MANURE, FOOD PROCESSING)
2C8 CROP RESIDUE
2LW LOGGING WASTES
2PT PROCESSING
2OT UTILIZATION
1AI AIR POLLUTION
2AN ANALYSIS
2C2 CONTROL EQUIPMENT
2DU DUMPS
2FD FEEDLOTS
2IC INCINERATOR
2IN INDUSTRY
2LF LAWS
2SQ SMOKE CONTROL
1AL ALGAE
(.See MICROORGANISM)
IAN ANALYSIS
1AQ ANIMALS
(See also MANURE)
2 CD CARCASS
2FD FEEDLOTS
2VC VECTOR CONTROL
1AS ASH
2CN COMPOSITION
2DP DISPOSAL
2UT UTILIZATION
1AU AUTOMOBILES
2BU BURNING
2CL COLLECTION
2C6 COSTS
2DP DISPOSAL
21C INCINERATION
2LF LAWS
2QU QUANTITY
2RT RAIL TRANSPORT
2TT TRANSPORT
2UT UTILIZATION
2VR VOLUME REDUCTION
1AY AUTOMOTIVE INDUSTRY
(See also AUTOMOBILES)
2DP DISPOSAL
2PT PROCESSING
2UT UTILIZATION
323
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HAZARDOUS WASTE MANAGEMENT
1BC
1BL
1BU
BACTERIA
CSee MICROORGANISMS)
1CF
1CH
BALING
2ET
2PD
2SC
BULKY WASTES
2CL
2 DP
2TT
2UT
2VR
CELLULOSE
CHEMICALS
2 IN
EQUIPMENT
PAPER
SCRAP METAL
COLLECTION
DISPOSAL
TRANSPORT
UTILIZATION
VOLUME REDUCTION
2PC
INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1CL
ICO
1CP
ICQ
COLLECTION
CSee also
2CJ
2CM
2CZ
2C1
2C6
2ET
2FR
2 IN
2IW
2LF
2MY
2PH
2PQ
2RO
2RW
2TU
COMPACTION
2ET
COMPOST
2AN
2 HE
2MG
2UT
COMPOSTING
2CC
2CF
2C6
2DP
2ET
2HE
2IC
2 IT
2LF
2MX
CONTAINERS)
CHUTE SYSTEMS
COMMERCIAL WASTES
CONTAINERS
CONTRACTORS
COSTS
EQUIPMENT
FREQUENCY
INDUSTRIAL WASTES
INSTITUTIONAL WASTES
LAWS
MUNICIPAL WASTES
PERSONNEL
PNEUMATIC
ROUTES
RURAL AREAS
TRUCKS
EQUIPMENT
ANALYSIS
HEALTH AND SAFETY
MARKETS
UTILIZATION
TANNERY WASTES
CELLULOSE
COSTS
DISPOSAL
EQUIPMENT
HEALTH AND SAFETY
INCINERATION
INSTALLATIONS
LAWS
METHODS
324
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HIERARCH TERMS
2PD PAPER
2PS PROBLEMS
2SI SEPARATION OF NON-ORGANICS
2SP SLUDGE
1CT COMPUTER
(See MANAGEMENT AND PLANNING)
1CX CONSTRUCTION
(See also DEMOLITION WASTES)
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1CZ CONTAINERS
2OP DISPOSAL
IDA DAIRY (INDUSTRY)
IDE DEEP WELL STORAGE
1DM DEMOLITION WASTES
(See also CONSTRUCTION)
1DP DISPOSAL
(See also INDIVIDUAL METHODS)
2AG AGRICULTURAL WASTES
2CM COMMERICAL WASTES
2C6 COSTS
2DG DREDGING
2FC FACILITIES
2HC HAZARDOUS WASTE
2HE HEALTH AND SAFETY
2IN INDUSTRIAL WASTES
2IW INSTITUTIONAL WASTES
2LF LAWS
2MX METHODS
2MY MUNICIPAL WASTES
2RP RESEARCH
2RV RURAL AREAS
1DR DRUGS
(See also PHARMACEUTICAL WASTES)
1DU DUMPS
2EL ELIMINATION
2HE HEALTH AND SAFETY
2LF LAWS
1EC ECONOMICS
2C6 COSTS
2MG MARKETS
2TX TAXES
1EI EDUCATION
2PH PERSONNEL
2PO PROFESSIONAL
2PV PUBLIC
325
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HAZARDOUS WASTE MANAGEMENT
1EN ENERGY
2EC ECONOMICS
2RD REFUSE DERIVED FUELS
2UT UTILIZATION
1EP ENVIRONMENTAL PROTECTION
1ET EQUIPMENT
2AN ANALYSIS
2BR BALERS
2CL COLLECTION
2CO COMPACTION
2C3 CONVEYOR
2HM HAMMERMILLING
2MH MATERIALS HANDLING
2SD SALVAGE AND RECLAMATION
2SG SANITARY LANDFILL
2SI SEPARATORS - FITTERS
2SK SHEARING
2SL SHREDDING
2SU SPREADING
2TT TRANSPORTATION
2WT WASTEWATER TREATMENT (CONTROL EQUIPMENT)
1FE FERTILIZER
(.See also COMPOST, HAZARDOUS)
2DP DISPOSAL
2RF REFUSE DERIVED FERTILIZER
1FI FIRE
1FL FLY ASH
2AN ANALYSIS
2DP DISPOSAL
2MS MINE STABILISATION
2RC RECOVERY OF CONSTITUENTS
2SS SOIL CONDITIONER
2UT UTILIZATION
3AR AGGREGATE
1FO FOOD PROCESSING WASTES
2BG BAGASSE
2BK BAKERY
2BP BIOLOGICAL PROCESS!*^
2BW BREWERY
2CC CANNERY
2CI CHEMICAL PROCESSING
2CK COFFEE
2DA DAIRY
2DP DISPOSAL
2FR FRUITS
2GF GRAIN AND FEED CROPS
2MF MEAT PACKING PLANTS
2MP MECHANICAL PROCESSING
2MU MOLASSES
2PA POULTRY
2SE SEAFOOD
2SO SLAUGHTERHOUSE
2SX SUGAR
2UT UTILIZATION
2VG VEGETABLE
1FO FUNGI
(See MICROORGANISMS)
1GA GARBAGE GRINDING
326
image:
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HIERARCH TERMS
1GL GLASS
2IN INDUSTRIAL PASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1GR GRANTS
1GW GROUND WATER
1HC HAZARDOUS WASTES
(See also RADIOACTIVE WASTES, HOSPITALS, PESTICIDES)
2AN ANALYSIS
2DP DISPOSAL
2PT PROCESSING
1HE HEALTH ANE SAFETY
1HH HEAT RECOVERY
(See INCINERATION)
1HO HOG FEEDING
IBS HOSPITALS
(See also INSTITUTIONAL WASTES; HAZARDOUS WASTES)
2CL COLLECTION
2DI DISPOSABLE ITEMS
2DP DISPOSAL
2HE HEALTH AND SAFETY
2IC INCINERATION
1IC INCINERATION
(See also SPECIFIC WASTES)
2AI AIR POLLUTION
2CM COMMERCIAL WASTES
2CQ COMPOSTING
2C6 COSTS
2EM EMISSIONS
2ET EQUIPMENT
2IN INDUSTRIAL WASTES
2IW INSTITUTIONAL WASTES
2LF LAWS
2MC MANAGEMENT AND PLANNING
2MY MUNICIPAL WASTES
2OS ON SITE
2PE PLANT DESIGN
2PG PLANT OPERATION
2PS PROBLEMS
2RS RESIDUE
2SD SALVAGE AND RECLAMATION
2WA WASTE HEAT UTILIZATION
2WE WATER POLLUTION
HE INCINERATOR
2FB FLUIDIZED BED
20P OPEN PIT
2RK ROTARY KILN
2SP SLUDGE
2ST SPECIAL PURPOSE
327
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HAZARDOUS WASTE MANAGEMENT
UN INDUSTRIAL WASTES
(See also SPECIFIC INDUSTRY, SPECIFIC TREATMENT METHODS)
2AN ANALYSIS
2BP BIOLOGICAL PROCESSING
2CG CENTRALIZED DISPOSAL PLANT?
2CI CHEMICAL PROCESSING
2C6 COSTS
2EF EFFLUENT CHARGES
2LF LAWS
2MP MECHANICAL PROCESSING
2MY MUNICIPAL WASTES
2PY PYROLYSIS
2SJ SEWAGE
2TT TRANSPORTATION
2UT UTILIZATION
IIS INSECTS
1IW INSTITUTIONAL WASTES
2DP DISPOSAL
2PT PROCESSING
2UT UTILIZATION
1LC LAGOONS
1LD LAND RECLAMATION
(See also MINES, SANITARY LANDFILL)
1LF LAWS
2CL COLLECTION
2DP DISPOSAL
2ER ENFORCEMENT
2FF FEDERAL
2IB INTERNATIONAL
2MB MUNICIPAL
2SW STATE
1LH. LEACHATE
(.See also SANITARY LANDFILL, WATER POLLUTION)
1LR LITTER
2CB CAMPAIGNS
2C6 COST OF REMOVAL
2RJ RECREATION AREAS
1LU LUMBER
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
IMA MANAGEMENT AND PLANNING
2C7 COUNTY
2FF FEDEPAL
2IB INTERNATIONAL
2MB MUNICIPAL
2RI REGIONAL
2RW RURAL
2SW STATE
2TQ TECHNIQUES
328
image:
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HIERARCH TERMS
1MB MANURE
CSee also ANIMALS)
2CE CATTLE
2HE HEALTH AND SAFETY
2PA POULTRY
2PT PROCESSING
2SL SHEEP
2SN STORAGE
2SZ SWINE
2UT UTILIZATION
IMG MARKETS
1MI METAL, FERROUS
2EC ECONOMICS
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2SC SCRAP
2SN SLAG
2SY SWARF
1MK METAL, NON-FERROUS
2AM ALUMINUM
2C4 COPPER
2EC ECONOMICS
2HV HEAVY
2LB LEAD
2NI NICKEL
2PK PRECIOUS METALS
2TI TIN
2ZI ZINC
1MM MICROORGANISMS
1MO MINERALS
1MR MINES
CSee also LAND RECLAMATION)
1MT MINING INDUSTRY
2DP DISPOSAL
2PT PROCESSING
2UT UTILIZATION
1MV MONITORING
1MY MUNICIPAL WASTES
(See also REFUSE)
2CO COMPACTION
2DP DISPOSAL
2SH SEPARATION
2TT TRANSPORT
2UT UTILIZATION
1NO NOISE
IOC OCEAN DISPOSAL
2AG AGRICULTURAL WASTES
2CM COMMERCIAL WASTES
2 IN INDUSTRIAL WASTES
329
image:
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HAZARDOUS WASTE MANAGEMENT
2IW INSTITUTIONAL WASTES
2IX INTERNATIONAL CONTROL
2MY MUNICIPAL WASTES
2SP SLUDGE
10F ODOR CONTROL
lOL OIL
IPS PACKAGING WASTES
2DP DISPOSAL
2PT PROCESSING
2UT UTILIZATION
1PD PAPER AND PULP
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2NE NEWSPAPERS
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1PF PATHOGENIC WASTES
1PH PERSONNEL
1PJ PESTICIDES
1PL PETROCHEMICALS
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2OI OIL SPILLS
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1PN PHARMACEUTICAL WASTES
1PP PLANNING
1PR PLASTICS
2 IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1PT PROCESSING
1PV PUBLIC RELATIONS
(See EDUCATION)
1PY PYROLYSIS
(See also INCINERATION)
1RD RADIOACTIVE WASTES
(See also HAZARDOUS WASTES)
330
image:
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HIERARCH TERMS
2 DP
2SW
DISPOSAL
STORAGE
1RG
1RJ
1RM
1RN
1RP
1RR
1RU
RECLAMATION
(See SALVAGE AND RECLAMATION)
RECREATIONAL AREAS
tSee also LAND RECLAMATION)
REDUCTION
REFUSE
(See also SPECIFIC TYPES)
2CA CALORIFIC VALUE
2CO COMPOSITION
2QU QUANTITY
RESEARCH
(See SPECIFIC TOPICS; GRANT)
RESOURCE RECOVERY
RUBBER
2 IN
2PC
2TS
INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
TIRES
1SB
1SD
1SF
1SG
1SI
1SJ
SAFETY
(See HEALTH AND SAFETY)
SALVAGE AND RECLAMATION
(See also SPECIFIC TYPES)
SAND
SANITARY LANDFILL
(See also LAND RECLAMATION; SPECIFIC WASTES)
2CQ COMPOSTING
2C6 COSTS
2DC DECOMPOSITION
2DS DESIGN
2ET EQUIPMENT
2GS GASSES
2GW GROUND WATER
2MC MANAGEMENT AND PLANNING
2OE OPERATIONS
2RL REGULATIONS
2SL SHREDDING
2SO SITES
SEPARATION
2CH CHEMICAL
2LS LIQUID-SOLID
2MD MECHANICAL
2ML METAL
2MX METHODS
2RN REFUSE
SEWAGE
(See also SLUDGE)
2AN ANALYSIS
331
image:
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HAZARDOUS WASTE MANAGEMENT
2BP BIOLOGICAL PROCESSING
2CI CHEMICAL PROCESSING
2C6 COSTS
2HE HEALTH AND SAFETY
2IP IRRADIATION PROCESSING
2MP MECHANICAL PROCESSING
2TT TRANSPORTATION
1SL SHREDDING
1SN SLAG
tSee METAL, FERROUS)
ISO SLAUGHTERHOUSE
CSee FOOD PROCESSING WASTES)
ISP SLUDGE
(See also INDUSTRIAL WASTES)
2AN ANALYSIS
2BP BIOLOGICAL PROCESSING
2CI CHEMICAL PROCESSING
2C6 COSTS
2DP DISPOSAL
2ET EQUIPMENT
2HE HEALTH AND SAFETY
2HP HEAT PROCESSING
2IP IRRADIATION PROCESSING
2MP MECHANICAL PROCESSING
2TT TRANSPORTATION
2UT UTILIZATION
1SR SNOW REMOVAL
1ST SOIL
1SU SOURCES OF INFORMATION
1SW STORAGE
2C2 CONTAINERS
2C6 COSTS
2LF LAWS
2MX METHODS
2SO SITES
1SX STREET CLEANING
1SY SURVEYS
1SZ SYSTEMS ANALYSIS
CSee MANAGEMENT AND PLANNING)
1TB TANNERY WASTES
1TE TEXTILES
2IN INDUSTRIAL WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
2PC POST CONSUMER WASTES
3DP DISPOSAL
3PT PROCESSING
3UT UTILIZATION
1TM TOXIC MATERIALS
(See also HAZARDOUS WASTES)
332
image:
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HIERARCH TERMS
1TR TRANSFER STATIONS
(See also COLLECTION)
ITT TRANSPORTATION
(See also SPECIFIC WASTES)
2C6 COSTS
2JMX METHODS
2PM PIPELINES
2PQ PNEUMATIC
2RB RAILROADS
2SN SHIPS
2TK TRUCKS
1TV TREATMENT
(See PROCESSING)
1TY TREES
(See BULKY WASTES; LUMBER)
1VC VECTOR CONTROL
(See ANIMALS; INSECTS)
1VG VEGETATION
1VR VOLUME REDUCTION
1WE WATER POLLUTION
(See also GROUND WATER)
2AG AGRICULTURAL WASTES
2AN ANALYSIS
2CM COMMERCIAL WASTES
2C2 CONTROL EQUIPMENT
2EC ECONOMICS
2HE HEALTH AND SAFETY
2IN INDUSTRIAL WASTES
2LF LAWS
2MY MUNICIPAL WASTES
2SJ SEWAGE
1WO WOOD
(.See LUMBER)
333
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Appendix E
GEOGRAPHIC CODES
1AF Africa
IAN Antarctica
IAS Asia
1AU Australia
1CA Canada
1CB Caribbean
1EU Europe
IMA Marshall Islands
1ME Mexico
1MI Middle East
1NZ New Zealand
ISA South America
1SU Soviet Union
1US United States
2AA Alabama
2AC Alaska
2AE Alberta
2AG American Samoa
2AI Arizona
2AN Argentina
2AR Arkansas
2AS Austria
2BE Belgium
2BI Brazil
2BR British Columbia
2CA California
2CH China (Mainland)
2CI China (Taiwan)
2CO Colorado
2CT Connecticut
2CZ Czechoslovakia
2DE Delaware
2DN Denmark
2DT District of Columbia
2FI Finland
2FL Florida
2FR France
2GB Gabon
2GE Georgia
2GM Germany (East)
2GN Germany (West)
2GU Guam
2HI Hawaii
2HK Hong Kong
2HU Hungary
2IA Idaho
211 Illinois
2IL India
2IN Indiana
210 Indonesia
2IQ Iowa
2IR Ireland
2IS Israel
2IT Italy
2JM Jamaica
2JP Japan
2KS Kansas
2Ky Kentucky
2LE Lebanon
2LI
2LT
2LU
2MA
2MD
2MH
2MI
2MJ
2MN
2MP
2MR
2MT
2NB
2NE
2NF
2NG
2NH
2NJ
2NM
2NQ
2NR
2NT
2NY
20H
20K
2ON
20R
2PC
2PE
2PJ
2PL
2PR
2RI
2SA
2SF
2SI
2SK
2SP
2SR
2SU
2SY
2TA
2TE
2TK
2TN
2UG
2UK
2UT
2VA
2VE
2V I
2VN
2VR
2WA
2WR
2WW
2WY
2YU
3AI
3AK
Libya
Lithuania
Louisiana
Maine
Maryland
Massachusetts
Melbourne
Michigan
Minnesota
Mississippi
Missouri
Montana
Nebraska
Nepal
Netherlands
Nevada
New Hampshire
New Jersey
New Mexico
New York
North Carolina
North Dakota
Norway
Ohio
Oklahoma
Ontario
Oregon
Pakistan
Pennsylvania
Peru
Poland
Puerto Rico
Rhode Island
Saskatchewan
South Africa
South Carolina
South Dakota
Spain
Sweden
Switzerland
Sydney
Tasmania
Tennessee
Texas
Thailand
Uganda
United Kingdom
Utah
Venezuela
Vermont
Victoria
Virginia
Virgin Islands
Washington
West Virginia
Wisconsin
Wyoming
Yugoslavia
Aiken
Akron
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GEOGRAPHICAL
SAL
3AM
3AS
3AT
3BA
3BC
3BI
3BK
3BL
3BN
3BR
3BS
3BT
3BV
3BW
3CA
3CD
3CF
3CI
3CJ
3CN
3CP
3CT
3CU
3CY
3CZ
3DE
3DI
3DN
3DT
3DU
3EB
3ED
3EK
3 EM
3EY
3FB
3FI
3FL
3FN
3FR
3SA
3SC
3SD
3SE
3SG
SSI
3SN
3SO
3SP
3SR
3ST
3SU
3TA
3TC
3TK
3TN
3TO
3TR
3TU
3VC
3GA
3GE
Albany
Ames
Amsterdam
Atlanta
Baltimore
Bangkok
Basel
Barking
Bavaria
Berkeley
Berlin
Birmingham
Boston
Bridgeport
Broward
Calumet
Camden
Casteljaloux
Cheshire
Chicago
Cincinnati
Cleveland
Clinton
Columbus
Cook
Czestochowa
Denver
Detroit
Dublin
Duluth
Dusseldorf
Ebingen
Edinburgh
Elk Creek
Elmira
Ely
Fairbanks
Finham
Flagstaff
Frankfort
Franklin
St. Croix
St. Joseph
St. Louis
St. Paul
St. Petersburg
San Diego
San Francisco
Santa Ana
Santa Barbara
Savannah
Stockholm
Stuttgart
Tel Aviv
Tocks Island
Tokyo
Toronto
Trenton
Tripoli
Tucson
Venice
Gainesville
Geneva
3GL Glasgow
3HA Hague
3HF Haifa
3HG Hamburg
3HJ Hanford
3HL Harlem
3HM Hartford
3HO Honolulu
3HR Hopewell
3HU Houston
3IT Ithaca
3JE Jerusalem
3JH Johannesburg
3JP Joplin
3KC Kansas City
3KH Karlsruhe
3KN Knox
3KS Kosovo
3KW Kracow
3LC Lancaster
3LI Lima
3LL Liverpool
3LO London
3LS Los Angeles
3LY Lycoming
3MA Madras
3MD Madrid
3MH Manchester
3MI Maui
3ML Melbourne
3MM Miami
3MO Milwaukee
3MP Minneapolis
3MR Mobile
3MT Montgomery
3MU Munich
3MY Muskegon
SNA Nashville
3ND New Delhi
3NL New Orleans
3NO New York City
3NR Niagara
3NU Nurnberg
30C Ochtrup
SOT Ottawa
3PA Paris
3PC Passaic
3PH Philadelphia
3PN Phoenix
3PS Pinellas
3PW Piscataway
3RC Rochester
3RO Rocky Flats
3VE Ventura
3VI Virginia Beach
3WA Walcheren
3WE Weidenau-Geisweid
3WK West Nyack
3WM Willamette River
3WY Winnebago
3YO Yosemite
3ZU Zurich
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Appendix F
DOCUMENT CATEGORY CODES
01 AGRICULTURAL WASTES
Crop residues
Manure
Timber/other vegetation
02 ANALYSIS OF SOLID WASTE
Data
03 AUTOMOBILES
04 BULKY WASTES
05 COLLECTION
06 COMPOST
07 DISPOSAL
08 ECONOMICS
Disposal costs
Financing facilities
Pollution control costs
Marketing information
Taxes and incentives
09 HAZARDOUS WASTES
10 HEALTH/SAFETY
11 INCINERATION
12 INDUSTRIAL WASTES
13 INSTITUTIONAL WASTES
14 LAWS/REGULATIONS
15 LITTER
16 MANAGEMENT
Municipal
Regional
Rural
State
17 OCEAN DISPOSAL
18 PACKAGING
19 PROCESSING/REDUCTION
20 RECYCLING
Incinerator residue
Industrial wastes
Mining wastes
Municipal refuse
Scrap metal
21 RESEARCH
22 SANITARY LANDFILL
23 SEPARATION
24 SLUDGE
25 STORAGE
26 STREET CLEANING
27 TRAINING, EDUCATION,
PUBLIC RELATIONS
28 TRANSPORT
29 SOURCE REDUCTION
30 ENERGY
Demand, for solicj waste
management
Fuel from wastes
Heat utilization from
incineration
ya 1787
SW-756
*U S. GOVERNMENT PRINTING OFFICE: 19T9 620-007/3781 1-3
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U.S. Envlronr-cntcl Protection Agency
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