Irradiation performance of HTGR recycle fissile fuel
The irradiation performance of candidate HTGR recycle fissile fuel under accelerated testing conditions is reviewed. Failure modes for coated-particle fuels are described, and the performance of candidate recycle fissile fuels is discussed in terms of these failure modes. The bases on which UO/sub 2/ and (Th,U)O/sub 2/ were rejected as candidate recycle fissile fuels are outlined, along with the bases on which the weak-acid resin (WAR)-derived fissile fuel was selected as the reference recycle kernel. Comparisons are made relative to the irradiation behavior of WAR-derived fuels of varying stoichiometry and conclusions are drawn about the optimum stoichiometry and the range of acceptable values. Plans for future testing in support of specification development, confirmation of the results of accelerated testing by real-time experiments, and improvement in fuel performance and reliability are described.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7154051
- Report Number(s):
- ORNL/TM-5502; TRN: 76-020773
- Country of Publication:
- United States
- Language:
- English
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COATED FUEL PARTICLES
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
HTGR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
RELIABILITY
ACCIDENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
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Nonbreeding
Graphite Moderated