Studies of Ceramic Fuels with Use of Fission Gas Release Loop, (IV)
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- HANDA Muneo
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- YAMAGISHI Shigeru
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- FUKUDA Takeshi
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- SHIBA Koreyuki
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- TAKAHASHI Yoshihisa
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- TANIFUJI Takaaki
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- OMORI Shunzo
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
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- KONDO Akinori
- Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute
書誌事項
- タイトル別名
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- Fission Gas Release from Uranium Carbide in the Presence of Trace Amounts of Water Vapor
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説明
In-pile release of fission gas from sintered UC pellets in the presence of 8230 ppm of water vapor in the He sweep gas was measured over the temperature range of 160°1, 000°C.A very complex release behavior was observed and the mechanisms of release were deduced from the manner in which the release depended on the decay constant. It was established that the release of short-lived fission gases during irradiation was controlled mainly by pseudo-recoil, while chemical reaction between UC and water vapor, as well as knock-out, appeared to con-tribute much more significantly in the case of the longer-lived fission gases. The release of fission gas after reactor shutdown was shown to be governed by the UC-H2O reaction. The ratio of the release due to this reaction in reference to the total release was found to be de-pendent not only on the concentration of the water vapor but also on the amount present of the accumulated reaction products. Also, a discussion is given on the inordinately high release of 135mXe observed at 600°C.
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) 11 (9), 387-394, 1974
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
- 1390001204098091392
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- NII論文ID
- 130000823701
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- COI
- 1:CAS:528:DyaE2MXitlWqsg%3D%3D
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- ISSN
- 18811248
- 00223131
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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
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可