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Comparison of the NRC fuel performance code FRAPCON-3 to independent data sources

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:552368
; ;  [1]
  1. Battelle-Pacific Northwest National Lab., Richland, WA (United States)
FRAPCON-3 is an updated version of the U.S. Nuclear Regulatory Commission single-rod steady-state fuel performance code FRAPCON-2. To provide improved predictions at high-burnup levels, the code has updated properties for fission gas release (FGR), fuel thermal conductivity, fuel relocation, contact gap conductance, cladding corrosion and hydriding, fuel swelling, and radial power distribution. A detailed discussion of these model modifications is provided in NUREG/CR-6534.
OSTI ID:
552368
Report Number(s):
CONF-971125--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English