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Author: E. R. Irish Publisher: ISBN: Category : Fission products Languages : en Pages : 18
Book Description
The Purex process is a continuous solvent extraction process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Author: E. R. Irish Publisher: ISBN: Category : Fission products Languages : en Pages : 18
Book Description
The Purex process is a continuous solvent extraction process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages : 252
Book Description
This report describes Purex Plant operations at Hanford for January 1962--December 1962. Solvent extraction and ion exchange processes and data are discussed.
Author: Publisher: ISBN: Category : Languages : en Pages : 241
Book Description
This report describes Purex Plant operations at Hanford for January, 1961-- December, 1961. Solvent extraction and ion exchange processes and data are discussed.
Author: Publisher: ISBN: Category : Languages : en Pages : 22
Book Description
The Process Specifications for Operational Control of the Purex Plant(l) have been revised to define the operational control changes as a result of (a) converting the Purex Plant from three to two cycles, and (b) the use of the Plutonium Anion Exchange Unit (N-Cell) for routine plutonium concentration in place of the L-Cell Concentration Package. The flowsheets specified in Figures I-1, -2, and -3, and Table I fulfill the requirements for nuclear and chemical safety within the process as defined in Purex Process Specifications. The flowsheet also provides adequate recovery and decontamination to meet the product purity requirements itemized in Section 3.04. To clarify the two-cycle flowsheet and to simplify its use, the specifications are listed on graphic flow diagrams with the notation that process control allows a deviation of plus or minus five percent on all specifications except TBP concentration in solvent.
Author: Publisher: ISBN: Category : Languages : en Pages : 100
Book Description
In keeping with the announced goals for production at Hanford, a series of separations plant studies is being conducted with the objective of providing an insight into worthwhile design development goals both process and plant-wise. These studies will provide a basis for evaluation of research and development programs, with all cost estimates and other supporting information standardized, both in presentation and detail. These developments are vital to the future of separations plant planning in order that proper emphasis be placed on the most economic production facility for HAPO, should production planning require an additional major facility. This report is the second of a series, reporting on the design developments under way. The purposes of this document are to present the results of the second separations plant design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve the significant capital and operating cost reductions indicated.
Author: Publisher: ISBN: Category : Languages : en Pages : 22
Book Description
This document is Revision No. 2 of the ''Process Specifications for Critical Mass Control -- Purex Plant''. It encompasses the changes in flowsheet, equipment and plant operating philosophy that have developed since the plant startup. It supersedes Document HW-44064 (Revision No. 1). Plutonium-239 and uranium-235, either as the metals or as dissolved or solid compounds are capable of spontaneous and violent nuclear reactions. Following initial dissolution of irradiated natural uranium fuel elements the Purex Plant is normally involved in the processing of liquid solutions containing these isotopes. However, in Purex Plant solutions, uranium-235 is invariably associated with a large fraction of neutron-absorbing uranium-238, a condition which precludes the possibility of a nuclear reaction. (These specifications are based on the premise that no enriched uranium is processed in the Purex Plant.) Plutonium-239, on the other hand, is separated from uranium by means of the Purex process; and even prior (process-wise) to its separation, the ratio of plutonium to uranium must be controlled during the off-standard conditions of plutonium rework or recycle. Critical mass control in the Purex Plant is concerned solely with prevention of nuclear reactions of plutonim-239, which has been produced by irradiation of natural uranium fuel elements.
Author: E. R. Irish
Author: E. R. Irish
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Author: B. F. Judson
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Author: Leland L. Burger
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