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EXPERIENCE WITH THE PLUTONIUM RECYCLE TEST REACTOR

Technical Report ·
OSTI ID:4726330
The Plutonium Recycle Test Reactor (PRTR) is an experimental facility designed to support the development of Pu fuel cycles in thermal power reactors. The reactor design is aimed at providing a versatile test facility with prototype power reactor operating conditions in which it is possible to demonstrate the feasibility of recycling Pu fuels. Information concerning experience with PRTR is presented in sections on fuel, loading, and reactor kinetics. Conclusions based on the flrst year's operation are included. (J.R.D.)
Research Organization:
General Electric Co. Hanford Atomic Products Operation, Richland
NSA Number:
NSA-17-019566
OSTI ID:
4726330
Report Number(s):
HW-75007(Paper 11)
Country of Publication:
Country unknown/Code not available
Language:
English

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