Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (US)
- Sponsoring Org.:
- US Department of Energy (US)
- OSTI Identifier:
- 750584
- Report Number(s):
- ANL/ED/CP-100465
TRN: US0003510
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Conference
- 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
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; PWR TYPE REACTORS; MATHEMATICAL MODELS; FISSION PRODUCT RELEASE; URANIUM DIOXIDE; FUEL ELEMENT FAILURE; DIFFUSION; STOICHIOMETRY
Citation Formats
Skim, Y S. Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods. United States: N. p., 1999.
Web.
Skim, Y S. Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods. United States.
Skim, Y S. 1999.
"Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods". United States. https://www.osti.gov/servlets/purl/750584.
@article{osti_750584,
title = {Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods},
author = {Skim, Y S},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/750584},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Nov 12 00:00:00 EST 1999},
month = {Fri Nov 12 00:00:00 EST 1999}
}
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