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in subjects: "Spent Fuels Reprocessing"  
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Flowsheet No. 1: Cesium isolation and packaging

Description: An engineering flowsheet has been prepared for the conversion of an aqueous slurry of cesium-zinc-ferrocyanide into a dry cesium chloride product by the calcination process. Flowsheet No. 1 defines a six-step batch-type calcination operation for processing the slurry into a dry powder for offsite shipment in bulk containers. Some of the advantages to this process are as follows: Product losses are expected to be small, estimated to be less than 0.03 percent; the equipment required to process a … more
Date: May 20, 1957
Creator: Wirta, R. W. & Koski, O. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, September 1957

Description: The September, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.
Date: October 22, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for December 1956

Description: The December, 1956 monthly report for the Chemical Processing Department of Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operations. (MB)
Date: January 21, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, November 1957

Description: The November, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: December 23, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, May 1957

Description: The May, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.(MB)
Date: June 21, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, October 1957

Description: Record highs were set for Pu output in separations plants and for amount of U processed in Purex. UO{sub 3} production and shipments exceeded schedules. Fabrication of 200 and 250 Model assemblies is reported. Unfabricated Pu production was 8.5% short. Nitric acid recovery in Purex and Redox is reported. Prototype anion exchange system for Pu was tested in Purex. Hinged agitator arms with shear pin feature was installed in UO{sub 3} plant H calciner. Operation of continuous type Task I, II faci… more
Date: November 22, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: February 1957

Description: This report from the Chemical Processing Department at HAPO, discusses the following: Production operation, purex operation, redox operation, finished products operation, power and general maintenance operation, financial operation, facilities engineering operation, research and engineering operation, and employee relations operation.
Date: March 21, 1957
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: July 1957

Description: This report, for July 1957 from the Chemical Processing Department at HAPO, discusses the following; Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: August 22, 1957
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: January 1957

Description: This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation, purex operation, redox operation, finished products operation, power and general maintenance operation, financial operation, facilities engineering operation, research and engineering operation, and employee relations operation.
Date: February 21, 1957
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of cesium from Purex plant wastes by metal ferrocyanides and ferricyanides II: Full level laboratory investigations

Description: Laboratory scale experiments with synthetic Purex 1WW and HAW have demonstrated the feasibility of recovering cesium by precipitation with metal ferrocyanides and ferricyanides. One method for recovery of cesium involves neutralization of the precipitate ferric hydroxide and sodium diuranate, and recovery of cesium from the supernate by precipitation with zinc ferrocyanide. Another method involves precipitation with nickel or ferric ferrocyanide from partially neutralized 1WW, or from HAW. The … more
Date: February 28, 1957
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, April 1957

Description: Two new production records were set during April, for processed U and Pu production. 0.9 tons sheared NRX fuel were dissolved in Redox. Discrepancies in Pu yield are being studied. Alternate methods of recovering Np are being evaluated. The Purex prototype facility will be converted to the anion exchange process. Alternate designs for a Purex miniature service dissolver were reviewed. The Purex HA column will be replaced.
Date: May 22, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, June 1957

Description: Purex and Redox plants operated satisfactorily. Pu production exceeded commitments. The continuous calciners in UO{sub 3} plant experienced difficulty, but the monthly commitment was exceeded. Capital costs for conversion of B plant to recover Cs and Ce have increased. For future processing of E metal, several 3-ton batches were dissolved in Redox. The continuous Task I prototype is being tested for startup of production facilities. Redox product solutions generally have higher waste losses tha… more
Date: July 22, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A critical review of alternate methods of Purex solvent treatment

Description: This document is a HAPO report dated September 20, 1957. At the time of this report, there had been many different methods suggested for improving the Purex organic recovery system. Some of these suggestions been tried in the plant and others had not. Information concerning this system and, particularly, methods for improving it were wide spread. At the time of this report was no immediate source of information available on the proposed and investigated methods for improving the Purex solvent r… more
Date: September 20, 1957
Creator: Gordon, N. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed Purex Phase II expansion program

Description: This letter dated March 8, 1957 summarizes the results of preliminary studies on the stepwise expansion of Purex facilities to the ultimate rate of 4.0 capacity factor, using a two-cycle flow-sheet. Briefly, it was suggested that Purex be expanded to the intermediate capacity of 3.5 capacity factor using available FY-1958 funds insofar as possible; decision to expand Purex to 4.0 capacity factor, could have been deferred for subsequent budgetary consideration.
Date: March 8, 1957
Creator: Michels, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Continuous dissolution of uranium fuel elements in a tower dissolver

Description: A continuous process for the dissolution of irradiated fuel elements is a potential means of solving criticality limitations in the dissolution of enriched uranium slugs and of achieving higher dissolver capacity in the Redox and Purex Plants. This report summarizes development studies aimed at determination of dissolution rates, effluent compositions, and effects of changes in operating conditions on mercury-catalyzed dissolution in a tower-type unit.
Date: June 18, 1957
Creator: Evans, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of Critical Mass document HW-44064 to the Purex Process

Description: This document is a supplementary operating guide to document HW-44064, ``Process Specifications for Critical Mass Control -- Purex Plant.`` It is primarily intended that this document illustrate the actual operational means of conforming to the limits of critical mass control as presented in HW-44064.
Date: February 5, 1957
Creator: Gustafson, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering study Purex two-cycle conversion

Description: Adoption of a two-cycle solvent extraction process at Purex, in place of the present three-cycle process, offers great potentialities for reduction of manufacturing costs, improved product and by product recovery and increased capacity. This report deals with the engineering feasibility of converting Purex for two-cycle operation.
Date: March 23, 1957
Creator: Carpenter, G. K.; LaRiviere, J. R. & Michels, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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