The melting temperature of irradiated oxide fuel

Junji Komatsu; Toshimichi Tachibana; Kenji Konashi

doi:10.1016/0022-3115(88)90116-X

The melting temperature of irradiated oxide fuel

Junji Komatsu, Toshimichi Tachibana, Kenji Konashi

Research output: Contribution to journal › Article › peer-review

23 Citations (Scopus)

Abstract

The melting temperature of oxide fuel is generally considered to decrease with increasing of burnup because of the buildup of fission products. Melting temperatures were measured for UO₂ and (U, Pu)O₂ fuels. The (U, Pu)O₂ specimens were irradiated to a burnup of 110 GWd/t in FBR. The solidus temperatures of (U, Pu)O₂ were almost independent of burnup up to 50 GWd/t. The melting temperatures were correlated with Pu content, oxygen-to-metal ratio of the fuel and burnup by ideal solution theory.

Original language	English
Pages (from-to)	38-44
Number of pages	7
Journal	Journal of Nuclear Materials
Volume	154
Issue number	1
DOIs	https://doi.org/10.1016/0022-3115(88)90116-X
Publication status	Published - 1988 Jun
Externally published	Yes

ASJC Scopus subject areas

Nuclear and High Energy Physics
Materials Science(all)
Nuclear Energy and Engineering

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10.1016/0022-3115(88)90116-X

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author = "Junji Komatsu and Toshimichi Tachibana and Kenji Konashi",

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AU - Tachibana, Toshimichi

AU - Konashi, Kenji

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AB - The melting temperature of oxide fuel is generally considered to decrease with increasing of burnup because of the buildup of fission products. Melting temperatures were measured for UO2 and (U, Pu)O2 fuels. The (U, Pu)O2 specimens were irradiated to a burnup of 110 GWd/t in FBR. The solidus temperatures of (U, Pu)O2 were almost independent of burnup up to 50 GWd/t. The melting temperatures were correlated with Pu content, oxygen-to-metal ratio of the fuel and burnup by ideal solution theory.

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The melting temperature of irradiated oxide fuel

Abstract

ASJC Scopus subject areas

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