Thermal Conductivity Measurements on UO_<2+x> from 300 to 1, 400 K
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概要
- 論文の詳細を見る
In order to evaluate the thermal conductivity of oxidized fuel pellets of leaker fuel rods, UO<SUB>2+x</SUB> samples with x between 0.00 and 0.20 were prepared by an oxidation or a sintering method. Sample thermal diffusivities were measured by using a laser flash method from 300 to 1, 400K and their thermal conductivities were evaluated from multiplying the thermal diffusivities by the sample densities and the specific heat capacities derived from the literature. The thermal conductivities of UO<SUB>2+x</SUB> were decreased with increasing hyperstoichiometry and they were expressed as a function of their hyperstoichiometry using the concentration of U<SUB>5+</SUB> formed with the excess interstitial oxygen atoms.
- 社団法人 日本原子力学会の論文
- 1996-08-25
著者
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Amaya M
Fuel Safety Research Group Nuclear Safety Research Center Japan Atomic Energy Agency
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Kubo Toshio
Nippon Nuclear Fuel Development Co. Ltd.
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AMAYA Masaki
Nippon Nuclear Fuel Development Co., Ltd.
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KOREI Yoshiaki
Nippon Nuclear Fuel Development Co., Ltd.
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Korei Yoshiaki
Nippon Nuclear Fuel Development Co. Ltd.
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Kubo Toshio
Nippon Nuclear Fuel Development Co., Ltd.
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