Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods
A simplified semi-empirical model predicting fission gas release form UO{sub 2+x} fuel to the fuel rod plenum as a function of stoichiometry excess (x) is developed to apply to the fuel of a defective LWR fuel rod in operation. The effect of fuel oxidation in enhancing gas diffusion is included as a parabolic dependence of the stoichiometry excess. The increase of fission gas release in a defective BWR fuel rod is at the most 3 times higher than in an intact fuel rod because of small extent of UO{sub 2} oxidation. The major enhancement contributor in fission gas release of UO{sub 2+x} fuel is the increased diffusivity due to stoichiometry excess rather than the higher temperature caused by degraded fuel thermal conductivity.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 750584
- Report Number(s):
- ANL/ED/CP-100465; TRN: US0003510
- Resource Relation:
- Conference: International Topical Meeting on Light Water Reactor Fuel Performance, Park City, UT (US), 04/10/2000--04/13/2000; Other Information: PBD: 12 Nov 1999
- Country of Publication:
- United States
- Language:
- English
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