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Adsorption of Young Fission Products on Various Surfaces from Neutral and Dilute Acid Media: Application to Water Sample Collection for Step Programs

Description: In the STEP reactor accident study programs, water samples and moisture-saturated atmosphere plateout samples will be submitted for analysis of various fission product nuclides.
Date: unknown
Creator: Foster, Robert E.; Maeck, William J. & Rein, James E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Processing of the Core Fuel Used Initially in the Experimental Breeder Reactor (EBR-I)

Description: A detailed description of the processing of enriched uranium from the first core of the EBR-I, together with cold runs preceding this active processing. The fuel and aluminum shipping cans were dissolved in nitric acid with mercury catalyst.
Date: unknown
Creator: Erhard, A. E.; Murray, C. L.; Murry, R. F.; Newby, B. J.; Rohde, K. L.; Schilling, F.-P.-- (Frank-Peter) et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pilot Plant Development of a Process for Separating Barium-140 from MTR Fuel

Description: Extensive full scale pilot plant studies, using unirradiated materials, of a precipitation process designed to separate 30,000 to 50,000 curie quantities of high purity barium-140 from a twenty-day-irradiated, two-day-cooled MTR fuel assembly were conducted. Centrifugation was employed to effect liquid-solid separations
Date: unknown
Creator: Legler, Billy Mason, 1925-; Chase, W. L.; Martin, M. D.; Paige, D. M. & Wrigley, P. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pilot Plant Development of a Process for Separating Barium-140 from MTR Fuel

Description: Extensive full scale pilot plant studies, using unirradiated materials of a precipitation process designed to separate 30,000 to 50,000 curie quantities of high purity barium-140 from a twenty-day-irradiated two-day-cooled MTR fuel assembly were conducted
Date: unknown
Creator: Legler, Billy Mason, |d 1925; Chase, W. L.; Martin, M. D.; Paige, D. M. & Wrigley, F. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of First Cycle Scrub Ration Reduction on Decontamination in the "25" Process

Description: The scrub flow ratio in the first cycle of the Hexone solvent extraction process for the recovery and decontamination of uranium from aluminum-uranium alloy fuels has been reduced by a factor of 10. A minimum flow ration of scrub : feed : extractant of 1: 79 : 67 has been plant-tested. Uranium losses were unaffected, and overall fission product decontamination for three cycles was changed only slighty
Date: unknown
Creator: Schilling, F.-P. (Frank-Peter)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiation Damage Problems in the ICPP Barium-140 Separation Process

Description: In the ICPP barium-140 separation process, an MTR fuel element is processed after only two days of cooling. Since the total activity present is of the order of 10(5) curies, it was necessary to investigate the extent and nature of radiation damage to process components, and to devise methods of protecting process solutions where necessary
Date: unknown
Creator: Andelin, Robert L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ICPP Input Measurement Program

Description: The measurement of residual fissionable material in spent reactor fuel elements requires specialized equipment, methods and control procedures. As a result of processing a variety of fuels at ICPP an integrated measurement generation, control and interpretation system has evolved which provides highly precise measurements from which plant material balances are constructed.
Date: unknown
Creator: Tingey, Fred H. & Rein, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report for October Through December 1957: Idaho Chemical Processing Plant

Description: Aluminum-uranium alloy was processed successfully through the ICPP continuous dissolving-TBP extraction system. Process and equipment changes resulted in reduced waste volume. Recovery of uranium from a second zirconium alloy core was initiated. Separation of barium-140 was continued
Date: unknown
Creator: Stevenson, C. E.; Paige, D. M.; Slansky, C. M. & Warzel, F. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report for July Through September 1957 : Idaho Chemical Processing Plant

Description: Plant modifications made during the reporting period to permit continuous dissolution of fuel shapes other than slugs, to improve solution transfer by air lifts in place of pumps, and to minimize waste volumes by raffinate recycle and elimination of jet dilutions were completed and successfully tested
Date: unknown
Creator: Stevenson, C. E.; Paige, D. M.; Slansky, C. M. & Warzel, F. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Integrated Pilot Plant Run

Description: When the CPM facility was built at the Idaho Chemical Processing plant several continuous processing of aluminum-enriched uranium fuel elements were designed with limited knowledge. Through the study of these effects on individual pieces of equipment several new processes were designed to address some of the early problems encountered.
Date: unknown
Creator: Lohse, G. E.; Chajson, L. & Griffin, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Solvent Extraction of Enriched Uranium

Description: A compilation of information on solvent extraction including the Hexone-25 process, TBP-25 process is presented. Information is also included on solvent extraction of combined fuels containing Zr and stainless steel compositions
Date: unknown
Creator: Griffin, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Treatment : Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant

Description: Acidic wastes from the recovery of enriched uranium from aluminum, zirconium, and stainless steel fuels at the Idaho Chemical Processing Plant are stored underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste tank farm as well as the methods of environmental disposal of low level wastes is described.
Date: unknown
Creator: Stevens, James Irwin, 1920-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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