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U.S. Department of Energy
Office of Scientific and Technical Information

Rod cluster fuel elements for water-cooled pressure tube reactors

Conference ·
OSTI ID:5016410
Four and seven rod cluster fuel elements have been tested under conditions approaching those anticipated for a Hanford New Production Reactor. Maximum coolant temperature in one test was 270/sup 0/C. Maximum power density was 15 watts/gram. Stainless steel clad unbonded elements were exposed to 2300 MWd/T. Zircaloy-2 clad unbonded elements were irradiated to 600 MWd/T. A flexible end fitting was found necessary to support cluster fuel in the pressure tube. A seven rod element with Zr-2 clad coextruded uranium rods has been built for a 2000 MWd/T test in Hanford KER Loop 1.
Research Organization:
Battelle Pacific Northwest Labs., Richland, Wash. (USA)
DOE Contract Number:
EY-76-C-06-1830
OSTI ID:
5016410
Report Number(s):
HW-56910; CONF-580503-1
Country of Publication:
United States
Language:
English