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Nuclear and chemical safety analysis: Purex Plant 1970 thorium campaign
The purpose of this document is to discuss the flowsheet and the related processing equipment with respect to nuclear and chemical safety. The analyses presented are based on equipment utilization and revised piping as outlined in the design criteria. Processing of thorium and uranium-233 in the Purex Plant can be accomplished within currently accepted levels of risk with respect to chemical and nuclear safety if minor instrumentation changes are made. Uranium-233 processing is limited to a rate of about 670 grams per hour by equipment capacities and criticality safety considerations. The major criticality prevention problems result from the potential accumulation of uranium-233 in a solvent phase in E-H4 (ICU concentrator), TK-J1 (IUC receiver), and TK-J21 (2AF pump tank). The same potential problems exist in TK-J5 (3AF pump tank) and TK-N1 (3BU receiver), but the probabilities of reaching a critical condition are not as great. In order to prevent the excessive accumulation of uranium-233 in any of these vessels by an extraction mechanism, it is necessary to maintain the uranium-233 and salting agent concentrations below the point at which a critical concentration of uranium-233 could be reached in a solvent phase.
Date:
May 22, 1970
Creator:
Boldt, A. L. & Oberg, G. C.
System:
The UNT Digital Library
Folder 2: business management development of an improved neutron activation prediction code system
None
Date:
April 22, 1970
Creator:
unknown
System:
The UNT Digital Library
Metallography of AISI 347 sheet (.016'') creep tested in GH$sub 2$ at Battelle
None
Date:
October 22, 1970
Creator:
unknown
System:
The UNT Digital Library
Reflector-nozzle design trade study. Trade study No. 780
None
Date:
May 22, 1970
Creator:
unknown
System:
The UNT Digital Library