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- AMAYA Masaki
- Nippon Nuclear Fuel Development Co., Ltd.
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- KUBO Toshio
- Nippon Nuclear Fuel Development Co., Ltd.
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- KOREI Yoshiaki
- Nippon Nuclear Fuel Development Co., Ltd.
書誌事項
- タイトル別名
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- Thermal Conductivity Measurements on UO
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In order to evaluate the thermal conductivity of oxidized fuel pellets of leaker fuel rods, UO2+x 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 UO2+x were decreased with increasing hyperstoichiometry and they were expressed as a function of their hyperstoichiometry using the concentration of U5+ formed with the excess interstitial oxygen atoms.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 33 (8), 636-640, 1996
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001204093732352
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- NII論文ID
- 10002075265
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK28XmtVGmtLg%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4060417
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可