Thermal Conductivity Measurements on UO2+x from 300 to 1,400 K.
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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.
Bibliographic Information
- Other Title
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- Thermal Conductivity Measurements on UO
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Abstract
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.
Journal
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- Journal of Nuclear Science and Technology
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Journal of Nuclear Science and Technology 33 (8), 636-640, 1996
Atomic Energy Society of Japan
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Details 詳細情報について
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- CRID
- 1390001204093732352
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- NII Article ID
- 10002075265
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- NII Book ID
- AA00703720
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- COI
- 1:CAS:528:DyaK28XmtVGmtLg%3D
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- ISSN
- 18811248
- 00223131
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- NDL BIB ID
- 4060417
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- Text Lang
- en
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- Data Source
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- Abstract License Flag
- Disallowed