Life Time Estimation for Cladding Tube Cracking Caused by Absorber Swelling of PWR RCCA Rodlets.
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- MATSUOKA Takanori
- Experiment Department, Nuclear Development Corporation
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- YONEZAWA Toshio
- Takasago Research & Development Center, Mitsubishi Heavy Industries, Ltd.
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- NAKAMURA Kazuhiro
- Takasago Research & Development Center, Mitsubishi Heavy Industries, Ltd.
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- MURAKAMI Kazuo
- Kobe Shipyard & Machinery Works, Mitsubishi Heavy Industries, Ltd.
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- SHIMIZU Juntarou
- Kobe Shipyard & Machinery Works, Mitsubishi Heavy Industries, Ltd.
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- NAGATA Tadahisa
- General Office of Nuclear and Fossil Power Production, The Kansai Electric Power Co., Inc.
書誌事項
- タイトル別名
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- Life Time Estimation for Cladding Tube
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Intergranular cracks of cladding tubes had been observed at the tips of the rodlets of PWR rod cluster control assemblies (RCCAs). Because RCCAs are important core components, an investigation was carried out to estimate their service life time.<BR>(1) As it is essential to know the effect of slumping of the neutron absorber for the life time estimation, tests on absorber material were carried out. Both the dynamic and static stresses of the absorber are sufficiently small compared with its mechanical characteristics and it is concluded that slumping does not occur.<BR>(2) The crack was initiated at the inner surface of the cladding tubes and Sipush et al. obtained an intergranular fracture surface in tensile tests of similar material at a very slow strain rate in an argon gas atmosphere. Therefore the mechanism of the intergranular crack of the cladding tube is not IASCC but irradiation assisted cracking (IAC) caused by an increase in hoop strain due to the swelling of the absorber and a decrease in elongation due to neutron irradiation.<BR>(3) The crack initiation limit of cylindrical shells made of low ductile material and subjected to internal pressure is determined in relation to the uniform strain of the material and is in accordance with that of the RCCA rodlets in an actual plant.<BR>From the above investigation, the method of estimating the life time and countermeasures for its extension are obtained.
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) 35 (8), 564-578, 1998
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
- 1390001204094897280
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- NII論文ID
- 10002079880
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK1cXmsVegsL8%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4541363
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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
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- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可