Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods

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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 ... continued below

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14 p.

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Skim, Y. S. November 12, 1999.

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Description

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.

Physical Description

14 p.

Notes

INIS; OSTI as DE00750584

Medium: P; Size: 14 pages

Source

  • International Topical Meeting on Light Water Reactor Fuel Performance, Park City, UT (US), 04/10/2000--04/13/2000

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  • Report No.: ANL/ED/CP-100465
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 750584
  • Archival Resource Key: ark:/67531/metadc710629

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • November 12, 1999

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 2:08 p.m.

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Skim, Y. S. Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods, article, November 12, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc710629/: accessed October 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.