Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels (open access)

Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and decontamination can be performed in existing facilities once the fueks have been placed in solution form.
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
System: The UNT Digital Library
Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives. (open access)

Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives.

To insure a full evaluation of the effects of in-reactor loops with respect to all phases of the Plutonium Recycle Program, a separate study of each loop has been undertaken. An initial study was carried out which analyzed the effects of in-reactor loops using the design criteria for the gas loop as a basis. As soon as the design criteria for the H2O high pressure loop became available, a more detailed evaluation was completed for that loop. Recent completion of the scope description of the PRTR fuel element rupture test loop now permits an individual evaluation of this loop.
Date: January 29, 1960
Creator: Peterson, R. E.
System: The UNT Digital Library