Transient Elongation of a Fresh Fuel Rod under Reactivity Initiated Accident Conditions.
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- ISHIJIMA Kiyomi
- Reactivity Accident Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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- NAKAMURA Takehiko
- Reactivity Accident Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Research Institute
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In-pile experiments of fresh fuel rods under reactivity initiated accident (RIA) conditions have been performed in the Nuclear Safety Research Reactor at the Japan Atomic Energy Research Institute in order to understand the basic pellet cladding mechanical interaction (PCMI) behavior. Rapid fuel pellet expansion due to a power excursion would cause radial and longitudinal deformation of the cladding. This PCMI could be one of the possible incipient failure modes of an embrittled cladding of a high burnup fuel under the RIA conditions. <BR>Basic PCMI behavior was studied by measuring cladding deformation of a fresh fuel rod without complicated irradiation effects. The transient elongation measurements of the fuel with two kinds of gap width indicated not only PCMI-induced cladding elongation, but also reduction of the pellet stack displacement by the cladding constraint. In the tests under a high-pressure and high-temperature condition simulating an operation condition of BWRs, additional ridge-type cladding deformation was generated due to the axial collapse of the cladding. A preliminary analysis for interpretation of the tests was made using a computer code for the transient analysis of fuel rods, FRAP-T6.
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 (3), 229-238, 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
- 1390001204094515968
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- NII論文ID
- 10002074400
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK28XisFejsrw%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
