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Isaacson, R.E.; Brownell, L.E.
Atlantic Richfield Hanford Co., Richland, Wash. (USA)1972
Atlantic Richfield Hanford Co., Richland, Wash. (USA)1972
AbstractAbstract
No abstract available
Primary Subject
Source
Aug 1972; 33 p; Symposium on the management of radioactive wastes from fuel reprocessing; Paris, France; 27 Nov 1972; CONF-721107--4
Record Type
Report
Literature Type
Conference
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Country of publication
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Newby, B.J.
Exxon Nuclear Idaho Co., Inc., Idaho Falls (USA)1980
Exxon Nuclear Idaho Co., Inc., Idaho Falls (USA)1980
AbstractAbstract
[en] Methods were scoped for converting the sodium-bearing waste stored at the Idaho Chemical Processing Plant into granular, free flowing solids by fluidized-bed calcination at 5000C. The most promising methods were addition of aluminum nitrate or aluminum nitrate, hydrofluoric acid, and calcium nitrate to sodium-bearing waste prior to calcination. These will be used as alternates to a method consisting of adding calcium nitrate to a blend of zirconium fluoride and sodium-bearing wastes prior to calcination. Problems could develop in calcining such a blend, storing the resulting calcine, or in obtaining enough zirconium fluoride waste to blend with sodium-bearing waste
Primary Subject
Source
Oct 1980; 69 p; Available from NTIS., PC A04/MF A01
Record Type
Report
Report Number
Country of publication
ALKALI METAL COMPOUNDS, ALKALINE EARTH METAL COMPOUNDS, ALUMINIUM COMPOUNDS, CALCIUM COMPOUNDS, CHEMICAL REACTIONS, DECOMPOSITION, FLUORIDES, FLUORINE COMPOUNDS, FUEL REPROCESSING PLANTS, HALIDES, HALOGEN COMPOUNDS, HYDROGEN COMPOUNDS, INORGANIC ACIDS, MANAGEMENT, NATIONAL ORGANIZATIONS, NITRATES, NITROGEN COMPOUNDS, NUCLEAR FACILITIES, OXYGEN COMPOUNDS, PYROLYSIS, TRANSITION ELEMENT COMPOUNDS, US AEC, US ERDA, US ORGANIZATIONS, WASTE MANAGEMENT, WASTE PROCESSING, ZIRCONIUM COMPOUNDS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Posey, J.C.
Oak Ridge National Lab., TN (USA)1980
Oak Ridge National Lab., TN (USA)1980
AbstractAbstract
[en] A process has been designed for the recovery of curium from purex waste. Curium and americium are separated from the lanthanides by a TALSPEAK extraction process using differential extraction. Equations were derived for the estimation of the economically optimum conditions for the extraction using laboratory batch extraction data. The preparation of feed for the extraction involves the removal of nitric acid from the Purex waste by vaporization under reduced pressure, the leaching of soluble nitrates from the resulting cake, and the oxalate precipitation of a pure lanthanide-actinide fraction. Final separation of the curium from americium is done by ion-exchange. The steps of the process, except ion-exchange, were tested on a laboratory scale and workable conditions were determined
Primary Subject
Source
Oct 1980; 100 p; Available from NTIS., PC A05/MF A01
Record Type
Report
Report Number
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, CARBOXYLIC ACIDS, CURIUM ISOTOPES, DIAGRAMS, DICARBOXYLIC ACIDS, EVEN-EVEN NUCLEI, HEAVY NUCLEI, INFORMATION, ISOTOPES, MANAGEMENT, NUCLEI, ORGANIC ACIDS, ORGANIC COMPOUNDS, RADIOISOTOPES, REPROCESSING, SEPARATION PROCESSES, WASTE MANAGEMENT, WASTE PROCESSING, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Fore, C.S.; Vaughan, N.D.; Hyder, L.K.
Oak Ridge National Lab., TN (USA)1980
Oak Ridge National Lab., TN (USA)1980
AbstractAbstract
[en] This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description
Primary Subject
Secondary Subject
Source
Oct 1980; 310 p; Available from NTIS., PC A14/MF A01
Record Type
Report
Literature Type
Bibliography
Report Number
Country of publication
Reference NumberReference Number
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Flowers, R.H.
UKAEA Authority Fuel Processing Directorate1982
UKAEA Authority Fuel Processing Directorate1982
AbstractAbstract
[en] The report falls under the headings: introduction; the nature of radioactive wastes; how to manage radioactive wastes; packaging of radioactive wastes (supervised storage; disposal); waste form evaluation and test requirements (supervised storage; disposal); conclusions. (U.K.)
Primary Subject
Source
Apr 1982; 21 p; ISBN 0-7058-0785-1; 

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Report
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Country of publication
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Mellinger, G.B.; Palmer, C.R.; Petkus, L.L.
Pacific Northwest Lab., Richland, WA (USA)1979
Pacific Northwest Lab., Richland, WA (USA)1979
AbstractAbstract
[en] Compositions and properties of glasses developed for vitrification of TRU incinerator ashes are presented. The effects on glasses of variations in the ash are explored. Preliminary experience with engineering-scale melting tests is reported
Primary Subject
Secondary Subject
Source
Sep 1979; 32 p; American Ceramic Society conference; New Orleans, LA, USA; 14 - 17 Oct 1979; CONF-791045--10; Available from NTIS., PC AA03/MF A01 as DE82005776
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kaufmann, F.; Weisenburger, S.; Koschorke, H.; Seiffert, H.
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)1981
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)1981
AbstractAbstract
[en] The waste gases with a temperature of more than 5000C are led to a replaceable solid bed filter with a filling of ceramic bodies. The ceramic bodies consist mainly of Al2O3, ZrO2 and SiO2 and are molten on the surface, which fixes the dust to them. (DG)
[de]
Die Abgase mit einer Temperatur von mehr als 5000C werden durch ein auswechselbares Festbettfilter mit einer Fuellung aus schuettbaren Keramikformkoerpern gefuehrt. Die Keramikformkoerper bestehen im wesentlichen aus Al2O3, ZrO2 und SiO2 und sind an der Oberflaeche geschmolzen, wodurch der Staub gebunden wird. (DG)Original Title
Verfahren zur Filterung von Staub aus radioaktiven Abgasen und Einrichtung zur Durchfuehrung des Verfahrens; Radioactive waste processing facilities
Primary Subject
Secondary Subject
Source
22 Jan 1981; 5 p; DE PATENT DOCUMENT 2731327/C/; Available from Deutsches Patentamt, Muenchen, Germany, F.R
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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Deichelbohrer, P.R.; Beitel, G.A.
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1981
Rockwell International Corp., Richland, WA (USA). Rockwell Hanford Operations1981
AbstractAbstract
[en] The arc saw is one of the key components of the Contaminated Equipment Volume Reduction (CEVR) Program. This report describes the progress of the arc saw from its inception to its current developmental status. History of the arc saw and early contributors are discussed. Particular features of the arc saw and their advantages for CEVR are detailed. Development of the arc saw including theory of operation, pertinent experimental results, plans for the large arc saw and advanced control systems are covered. Associated topics such as potential applications for the arc saw and other arc saw installations in the world is also touched upon
Original Title
Arc saw
Primary Subject
Source
28 Sep 1981; 90 p; Available from NTIS., PC A05/MF A01 as DE82007073
Record Type
Report
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Reference NumberReference Number
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McCoy, M.W.; Allen, R.P.; Arrowsmith, H.W.
Pacific Northwest Lab., Richland, WA (USA)1980
Pacific Northwest Lab., Richland, WA (USA)1980
AbstractAbstract
[en] This paper summarizes work in progress at Pacific Northwest Laboratory to develop vibratory finishing into a large-scale decontamination system that can minimize the volume of surface-contaminated metallic and nonmetallic waste requiring geologic disposal. Vibratory finishing is a mass finishing process used in the metal finishing industry to debur, clean and improve surface finishes. The process combines a mechanical scrubbing action of a solid medium with the cleaning action of a liquid compound. The process takes place in a vibrating tub. Tests have demonstrated the ability to rapidly reduce contamination levels of transuranic-contaminated waste to substantially less than 10 nCi/g, the current limit for transuranic waste. The process is effective on a wide range of materials including stainless steel, Plexiglas, Neoprene, and Hypalon, the principal materials in Hanford glove boxes
Primary Subject
Secondary Subject
Source
Apr 1980; 22 p; 89. annual meeting of the American Institute of Chemical Engineers; Portland, OR, USA; 17 - 20 Aug 1980; CONF-800802--28; Available from NTIS., PC A02/MF A01 as DE82007084
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ALLOYS, CARBON ADDITIONS, CHROMIUM ALLOYS, CLEANING, CORROSION RESISTANT ALLOYS, DATA, ELASTOMERS, ESTERS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, LABORATORY EQUIPMENT, MACHINING, MANAGEMENT, NUMERICAL DATA, ORGANIC CHLORINE COMPOUNDS, ORGANIC COMPOUNDS, ORGANIC HALOGEN COMPOUNDS, ORGANIC POLYMERS, POLYACRYLATES, POLYMERS, POLYVINYLS, STEELS, SURFACE FINISHING, TRANSITION ELEMENT ALLOYS, WASTE MANAGEMENT, WASTE PROCESSING
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Egnell, J.; Larsen, J.G.; Moeller, L.; Roed, G.
Swedish Nuclear Fuel Supply Co., Stockholm1981
Swedish Nuclear Fuel Supply Co., Stockholm1981
AbstractAbstract
[en] Metastable liquid-liquid separation in glasses can often cause significant changes in physical and chemical properties of the original homogeneous glass. In some technical borosilicate glasses this phenomenon is used to change the chemical durability of the glass. For potential nuclear-waste-glasses the slow cooling through the temperature range 5500C - 7000C may lead to such a liquid-liquid phase separation. In order to investigate the susceptibility of phase separation of nuclear-waste-glasses, two KBS model glasses, ABS-39 and ABS-41, were investigated. Two of the subsequent reports are concerned with this problem. The third report also takes into consideration the effects of MoO3 on the immiscibility gap. The maximum amount of MoO3 that can be dissolved in ABS-39 and ABS 41 is also determined. (Auth.)
Primary Subject
Source
Dec 1981; 48 p; Made up of 3 reports of work financed by SKBF, peformed at the Technical University of Denmark.
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Report
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