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Nuclear waste management. Quarterly progress report, July--September 1977

Description: Significant research during this period was reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification processes; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management studies and safety assessment; waste isolation safety assessment; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. (DLC)
Date: January 1, 1978
Creator: Platt, A.M.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management quarterly progress report, April--June 1977

Description: Progress is reported in sections on decontamination and densification of chop-leach cladding residues, monitoring methods for effluents from waste solidification, TRU waste fixation studies, krypton solidification, /sup 14/C and /sup 129/I fixation, waste management system studies, waste isolation assessment, stored waste migration monitoring, properties of fission product organic complexes, and decontamination of metals. (JRD)
Date: November 1, 1977
Creator: Platt, A.M. (comp.)
Partner: UNT Libraries Government Documents Department
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QUARTERLY PROGRESS REPORT Research and development activities: fixation of radioactive residues. July-September 1965

Description: The calcined-waste containers produced during the Hot Cell Pilot Plant experiments in 1962 and 1963 have generated a maximum pressure of 3 psig. Design verification tests with the prototype spray calciner showed satisfactory performance when producing high melting point powders. Later tests on other feeds showed poor atomization and cake buildup in the calciner. Design of the prototype equipment is complete. Procurement and fabrication of prototype equipment is done except for a few cleanup items and final field-fitting of jumpers. Design verification tests on the pot storage station indicated satisfactory calorimeter performance. A GE-412 computer was successfully used in design verification tests for data collection, calculation, and correlations. Studies continued on fixation of sulfates from acid condensates generated in a glass-making process. Lead sulfate-borax melts produced by a continuous feed melter at 900/sup 0/C appear to be quite fluid, but exhibited a high (22%) evolution of sulfate. Studies were initiated on incorporation of the neutralized condensate into asphalt. Release rates of up to 2%/hr for /sup 137/Cs from a simulated phosphate ceramic waste material were observed from exposures to temperatures up to 1200/sup 0/C. Release rates of other isotopes which appear to be a thousand-fold lower than for cesium established volatilization as the predominant mode of cesium release. A technique for varying the phosphate content of the simulated ceramic wastes was developed.
Date: October 1, 1965
Creator: Platt, A.M. (ed.)
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, October--December 1977

Description: Work on the following is reported: decontamination and densification of chop-leach cladding residues, monitoring methods for particulate and gaseous effluents from waste solidification processes, TRU waste fixation studies, krypton solidification, /sup 14/C and /sup 129/I fixation, system studies, safety assessment, waste isolation safety assessment program, monitoring and physical characterization of unsaturated zone transport, detection and characterization of mobile organic complexes of fission, and electropolishing for surface decontamination of metals.
Date: May 1, 1978
Creator: Platt, A.M. (comp.)
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Management and Transportation quarterly progress report, October--December 1975

Description: Research is reported on advanced methods for waste management and disposal, decontamination and densification of chop-leach cladding residues, pyrolysis-incineration of combustible alpha wastes, tritium separation and fixation, disposition of retired contaminated facilities at Hanford, transportation safety studies, safety and economics of special trains, and high-level waste shipping cask models. (DLC)
Date: March 1, 1976
Creator: Platt, A. M. (comp.)
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Management quarterly progress report, October--December 1976

Description: Research topics on which progress is reported include decontamination and densification of chop-leach cladding residues, monitoring of effluents from waste solidification, TRU waste fixation, krypton solidification, /sup 14/C and /sup 129/I fixation, waste management system studies, organic complexes of fission products, characterization of 300 Area burial grounds, electropolishing as a decontamination technique, and decommissioning of Hanford facilities. 11 tables, 18 figures. (DLC)
Date: April 1, 1977
Creator: Platt, A. M. (comp.)
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Management and Transportation quarterly progress report, January--March 1976

Description: Progress is reported in the following areas: Alternative waste management systems; decontamination and densification of chop-leach cladding residues; tritium separation and fixation; disposition of retired contaminated facilities at Hanford; transportation safety studies; transport problems, 1976-2000; safety and economic study of special trains; and development of high-level waste shipping cask models. (LK)
Date: June 1, 1976
Creator: Platt, A. M. (comp.)
Partner: UNT Libraries Government Documents Department
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Nuclear Waste Management and Transportation quarterly progress report, April--June 1976

Description: Status of the following programs is reported: Alternative waste management systems; decontamination and densification of chop-leach cladding residues; disposition of retired contaminated facilities at Hanford; transportation safety studies; transport problems, 1976-2000; safety and economic study of special trains; and development of high-level waste shipping cask models. (LK)
Date: October 1, 1976
Creator: Platt, A. M. (comp.)
Partner: UNT Libraries Government Documents Department
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Nuclear waste management quarterly progress report, January--March 1977

Description: Status of the following studies is reported: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluent from waste solidification processes; TRU waste fixation studies; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system studies; waste isolation safety assessment program; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; characterization of 300 area burial grounds and electropolishing as a decontamination technique. (LK)
Date: July 1, 1977
Creator: Platt, A. M. (comp.)
Partner: UNT Libraries Government Documents Department
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Commercial US nuclear reactors and waste: the current status

Description: Between March 1 and June 15, 1980, the declared size of the commercial light waste reactor (LWR) nuclear power industry in the US has decreased another 9 GWe. For the presently declared size: the 165 declared reactors will peak at a capacity of 153 GWe in 2001 and will consume about 870,000 MTU as enrichment feed; the theoretical rate of enrichment requirements will peak at about 19,000,000 SWUs/y in the year 2014; as few as two repositories each with capacity equivalent to 100,000 MTU would hold the waste; and predisposal storage reactor basins and AFRs (away-from-reactor basins) would peak at <85,000 MTU in the year 2020 if the two respositories were commissioned in the years 1997 and 2020. It should be noted that the number of declared LWRs has dropped from 226 on December 31, 1974 to 165 as of this writing. The oil equivalent of the energy loss, assuming a 50% efficiency in use as in cars, is 17,000 million barrels. This is about 10 years of the current rate of US consumption of OPEC oil.
Date: September 1, 1980
Creator: Platt, A.M. & Robinson, J.V.
Partner: UNT Libraries Government Documents Department
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Commercial nuclear reactors and waste: the current status

Description: During the last five years, the declared size of the commercial light water reactor (LWR) nuclear power industry in the US has steadily decreased. As of January 1980, the total number of power plants had dropped to 191 from the 226 in December 31, 1974. At least another nine were cancelled in the last few months. This report was developed as the first of a series to track implications to waste management due to such changes in the declared size of the industry. For the presently declared size, key conclusions are: the declared reactors will peak at a capacity of 162 GWe and consume about 10/sup 6/ MTU as enrichment feed. As few as two repositories of about 100,000 MTHM capacity each would hold the waste. Predisposal storage (reactor basins and AFRs) would peak at less than 100,000 MTHM (in the year 2020) with one repository opening in the year 1997 and the other in the year 2020. Most of the 100,000 MTHM would have to be in AFR storage unless current practice regarding reactor basin size was radically changed.
Date: April 1, 1980
Creator: Platt, A.M. & Robinson, J.V.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, July-September 1979

Description: Research is reported on: decontamination and densification of chop-leach cladding residues, monitoring of effluents from waste solidification, TRU waste mobilization, Kr solidification, /sup 14/C and /sup 129/I fixation, waste management system and safety studies, waste isolation safety assessment, logging systems for shallow land burial, unsaturated zone transport, mobile organic complexes of fission products, electropolishing for surface decontamination of metals, and decontamination and decommissioning of Hanford facilities. (DLC)
Date: November 1, 1979
Creator: Platt, A.M. & Powell, J.A.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management quarterly progress report, October--December 1978

Description: The status of the following studies is given: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification processes; TRU waste immobilization; krypton sodidification; carbon-14 and iodine-129 fixation; waste management system; waste management safety; waste isolation safety assessment; well-logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. (LK)
Date: March 1, 1979
Creator: Platt, A.M. & Powell, J.A.
Partner: UNT Libraries Government Documents Department
open access

Nuclear waste management quarterly progress report, April--June 1978

Description: Work is reported in the following: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification processes; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; system studies; safety studies; waste isolation safety assessment; well logging instrumentation for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 25 figures, 10 tables. (DLC)
Date: November 1, 1978
Creator: Platt, A.M. & Powell, J.A.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, July--September 1978

Description: Research on the following is reported: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification processes; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system studies; waste management safety studies; waste isolation safety assessment; well logging instrumentation for shallow land burial; monitoring and physical characteriztion of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 21 figures, 17 tables.
Date: January 1, 1979
Creator: Platt, A. M. & Powell, J. A.
Partner: UNT Libraries Government Documents Department
open access

Nuclear waste management quarterly progress report, January--March 1978

Description: Significant research during this period was reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste-solidification processes; TRU waste immobilization program; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system studies; waste management safety studies; waste isolation safety assessment program; well logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. (LK)
Date: August 1, 1978
Creator: Platt, A. M. & Powell, J.A.
Partner: UNT Libraries Government Documents Department
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Research and development plans for disposal of high-level and transuranic wastes

Description: This plan recommends a 20-year, 206 million (1975 $'s) R and D program on geologic structures in the contiguous U.S. and on the midplate Pacific seabed with the objective of developing an acceptable method for disposal of commercial high-level and transuranic wastes by 1997. No differentiation between high-level and transuranic waste disposal is made in the first 5 years of the program. A unique application of probability theory to R and D planning establishes, at a 95% confidence level, that the program objective will be met if at least fifteen generic options and five specific disposal sites are explored in detail and at least two pilot plants are constructed and operated. A parallel effort on analysis and evaluation maximizes information available for decisions on the acceptability of the disposal techniques. Based on considerations of technical feasibility, timing and technical risk, the other disposal concepts, e.g., ice sheets, partitioning, transmutation and space disposal cited in BNWL-1900 are not recommended for near future R and D.
Date: September 1, 1978
Creator: Bartlett, J.W. & Platt, A.M.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, April-June 1980

Description: The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.
Date: September 1980
Creator: Platt, A. M. & Powell, J. A.
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, January-March 1980

Description: Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)
Date: June 1, 1980
Creator: Platt, A.M. & Powell, J.A. (comps.)
Partner: UNT Libraries Government Documents Department
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Nuclear waste management. Quarterly progress report, October-December 1979

Description: Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)
Date: April 1, 1980
Creator: Platt, A.M. & Powell, J.A. (comps.)
Partner: UNT Libraries Government Documents Department
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Characterization of nuclear waste

Description: Nuclear wastes which are logical candidates for deep geologic disposal include commercial (spent fuel, reprocessing) and defense wastes. It is expected that the 5250 metric tons of spent fuel discharged through the end of 1978 would increase to about 100,000 tons by the end of 2000. The individual characteristics of each waste type (spent fuel, solidified waste, defense wastes) are described in turn. (DLC)
Date: February 14, 1979
Creator: Platt, A. M.
Partner: UNT Libraries Government Documents Department
open access

Nuclear waste management. Quarterly progress report, April-June 1979

Description: Progress is reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification process; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system and safety studies; waste isolation safety assessment; well logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 9 figures, 14 tables. (DLC)
Date: September 1, 1979
Creator: Platt, A.M. & Powell, J.A. (comps.)
Partner: UNT Libraries Government Documents Department
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