Xenon Diffusivity in Thoria-Urania Fuel

Journal Article · Thu Jul 15 04:00:00 EDT 2004 · Nuclear Technology

OSTI ID:20840211

Kim, Heemoon ^[1]; Park, Kwangheon ^[2]; Kim, Bong Goo ^[1]; Choo, Yong Sun ^[1]; Kim, Keon Sik ^[1]; Song, Kun Woo ^[1]; Hong, Kwon Pyo ^[1]; Kang, Young Hwan ^[1]; Ho, Kwangil ^[3]

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1. Korea Atomic Energy Research Institute (Korea, Republic of)
2. Kyunghee University (Korea, Republic of)
3. Suwon University (Korea, Republic of)

Postirradiation annealing tests were performed to obtain the {sup 133}Xe diffusion coefficients in uranium dioxide (UO{sub 2}) and mixed thorium-uranium dioxide [(Th-U)O{sub 2}] fuels. Specimens were a single-grained UO{sub 2}, a polycrystalline UO{sub 2}, and a polycrystalline (Th-U)O{sub 2}. The (Th-U)O{sub 2} specimen was a mixture of 35% ThO{sub 2} and 65% UO{sub 2}. Each 300-mg specimen was irradiated to a burnup of 0.1 MWd/t U. Postirradiation annealing tests were performed at 1400, 1500, and 1600 deg. C, continuously. The xenon diffusion coefficients for the nearly stoichiometric single-grained UO{sub 2} agree well with the data of others. The xenon diffusion coefficients in the polycrystalline (Th-U)O{sub 2} are approximately one order lower than those in the polycrystalline UO{sub 2}. The xenon diffusion coefficient in the (Th-U)O{sub 2} increases with the increasing oxygen potential of the ambient gas.

• OSTI ID: 20840211
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 147; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ANNEALING
BURNUP
DIFFUSION
IRRADIATION
MIXED OXIDE FUELS
MIXTURES
OXYGEN POTENTIAL
POLYCRYSTALS
STOICHIOMETRY
THORIUM
THORIUM OXIDES
URANIUM DIOXIDE
XENON
XENON 133