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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.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Division monthly report, October 1966

Description: October performance of the plant production facilities was outstanding (915.2 tons U processed by Purex; 625.4 kg Pu separated by Redox/Purex). Redox processed three types of feed. Operation of incinerator furnace was resumed in Pu finishing processes. Capital cost estimates were prepared for several schemes for power reactor fuel reprocessing in Redox. Redox encased waste lines and line support system were found to be in good condition. H concentration in Redox dissolver off-gases occasionally… more
Date: November 21, 1966
Partner: UNT Libraries Government Documents Department
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Plutonium Finishing Plant Transition Project mission analysis report

Description: This report defines the mission for the Plutonium Finishing Plant Transition Project (PFPTP) using a systems engineering approach. This mission analysis will be the basis for the functional analysis which will further define and break down the mission statement into all of the detailed functions required to accomplish the mission. The functional analysis is then used to develop requirements, allocate those requirements to functions, and eventually be used to design the system. This report: pres… more
Date: September 21, 1994
Creator: Courson, D. B.
Partner: UNT Libraries Government Documents Department
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Ion Replacement Electrorefining

Description: We are developing a two-step electrochemical process for purifying and separating metals called ion replacement electrorefining. In each step, metal cations formed by oxidation at an electrode replace other metal cations that are reduced at another elecmae. Using this approach, we have separated or purified uranium, dysprosium, and lanthanum on a laboratory scale. This paper explains the ion replacement concept and presents results of these demonstration experiments.
Date: April 1, 1994
Creator: Willit, J. L.; Tomczuk, Z.; Miller, W. E. & Laidler, J. J.
Partner: UNT Libraries Government Documents Department
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History of 232-F, tritium extraction processing

Description: In 1950 the Atomic Energy Commission authorized the Savannah River Project principally for the production of tritium and plutonium-239 for use in thermonuclear weapons. 232-F was built as an interim facility in 1953--1954, at a cost of $3.9M. Tritium extraction operations began in October, 1955, after the reactor and separations startups. In July, 1957 a larger tritium facility began operation in 232-H. In 1958 the capacity of 232-H was doubled. Also, in 1957 a new task was assigned to Savannah… more
Date: August 1, 1994
Creator: Blackburn, G. W.
Partner: UNT Libraries Government Documents Department
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Report of clean out and flushing of UO{sub 3} Plant processing equipment: Revision 1

Description: The UO{sub 3} Plant went through a clean out leading to the deactivation of the facility. This clean out consisted of three phases. Phase 1 consisted of the removal of residual process material and the deactivation of most process equipment and instrumentation. Phase 2 consisted of the fixing or removal of contamination so storm water processing would be no longer required. Phase 3 consisted of the remaining activities that had to be completed before the facility was turned over to the Surplus … more
Date: December 2, 1994
Creator: Gonsalves, E.
Partner: UNT Libraries Government Documents Department
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Redox Committee: Conference notes and recommendations, meeting of June 23, 1949

Description: Topics discussed include gang valve substitute devices; cost of lining cell bottom with stainless steel; and the pump development program. [The Redox plant used a reduction-oxidation process for fuel separation that allowed recovery of uranium as well as plutonium for the first time. It succeeded earlier plants (T and B) that had used methods based on the bismuth phosphate process that recovered only plutonium.]
Date: June 23, 1949
Partner: UNT Libraries Government Documents Department
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Dissolver production tests

Description: In order to obtain data for the development and design of the Purex dissolvers and to demonstrate to Manufacturing and Technical personnel the feasibility of increasing the size of dissolver cuts at BiPO{sub 4} and Redox, a dissolver production test program in a BiPO{sub 4} dissolver is requested. These tests are expected to supplement the program already initiated on the 321 Bldg. dissolver, explaining dissolver behavior to the extent that existing dissolvers can be operated under more nearly … more
Date: August 5, 1952
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
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