The rim effect and other high-burnup modeling for NRC fuel performance codes
Conference
·
OSTI ID:54615
- Pacific Northwest Lab., Richland, WA (United States)
The U.S. Nuclear Regulatory Commission (NRC) has recently initiated a new program to review data on the material properties of fuel and cladding at high burnup levels. The objective of this program is to update NRC fuel performance models within fuel performance codes to improve their predictive capability to rod-average burnup levels of 60 GWd/MTM. Models being reviewed for improvement at the higher burnup levels are fission gas release, fuel swelling, gap conductance, fuel thermal conductivity, pellet rim structure, radial power distribution, cladding corrosion/hydriding, and cladding mechanical properties.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
- OSTI ID:
- 54615
- Report Number(s):
- NUREG/CP--0139; CONF-9410216--; ON: TI95001469
- Country of Publication:
- United States
- Language:
- English
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