Fission gas behavior in mixed-oxide fuel during transient overpower and simulated loss-of-flow tests

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A portion of the fission gases (Xe, Kr) generated during steady state irradiation of an FBR mixed-oxide fuel is retained within its microstructure, especially in the cooler regions of the fuel. Information on the behavior of these retained gases relative to their microstructural relocation and release during off-normal power and coolant flow conditions is important to the analysis and analytic modeling of fuel-pin transient and reactor core performance. This paper discusses the steady state and transient behavior of retained fission gas relative to the geometry, microstructure, temperature, and apparent release mechanisms within selected axial and radial regions of fuel pins ... continued below

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Pages:3

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Randklev, E.H. & Hinman, C.A. January 1, 1979.

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Description

A portion of the fission gases (Xe, Kr) generated during steady state irradiation of an FBR mixed-oxide fuel is retained within its microstructure, especially in the cooler regions of the fuel. Information on the behavior of these retained gases relative to their microstructural relocation and release during off-normal power and coolant flow conditions is important to the analysis and analytic modeling of fuel-pin transient and reactor core performance. This paper discusses the steady state and transient behavior of retained fission gas relative to the geometry, microstructure, temperature, and apparent release mechanisms within selected axial and radial regions of fuel pins irradiated at medium power (7 to 10 kW/ft) and burnup (30 to 60 MWd/kgm). The specific fuel pins are from the PNL-10 and PNL-2 subassemblies irradiated in EBR-II. The transient overpower tests involved integral fuel pin static capsule experiments performed in TREAT. Loss-of-coolant flow was simulated in an out-of-reactor thermal transient testing system using axial segments of irradiated fuel pins.

Physical Description

Pages:3

Notes

Dep. NTIS, PC A02/MF A01.

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  • International conference on fast breeder reactor performance, Monterey, CA, USA, 5 Mar 1979

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  • Report No.: HEDL-SA-1552-S
  • Report No.: CONF-790306-23
  • Grant Number: EY-76-C-14-2170
  • Office of Scientific & Technical Information Report Number: 6265386
  • Archival Resource Key: ark:/67531/metadc1109869

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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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  • January 1, 1979

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  • Feb. 22, 2018, 7:45 p.m.

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  • March 23, 2018, 4:24 p.m.

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Randklev, E.H. & Hinman, C.A. Fission gas behavior in mixed-oxide fuel during transient overpower and simulated loss-of-flow tests, article, January 1, 1979; United States. (digital.library.unt.edu/ark:/67531/metadc1109869/: accessed April 26, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.