Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 14 pages : digital, PDF file
Additional Creators:: Argonne National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

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 UO₂ 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.

Report Numbers:

E 1.99:anl/ed/cp-100465
anl/ed/cp-100465

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Note:

Published through SciTech Connect.
11/12/1999.
"anl/ed/cp-100465"
International Topical Meeting on Light Water Reactor Fuel Performance, Park City, UT (US), 04/10/2000--04/13/2000.
Skim, Y. S.

Funding Information:

W-31109-ENG-38

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