ICONE19-43600 STUDY ON IN-SERVICE INSPECTION AND REPAIR PROGRAM AND RELATED PLANT DESIGN FOR JAPAN SODIUM-COOLED FAST REACTOR (JSFR)
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- Kubo Shigenobu
- Japan Atomic Power Company (JAPC)
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- Suzuki Shinichi
- Japan Atomic Power Company (JAPC)
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- Kotake Shoji
- Japan Atomic Power Company (JAPC)
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- Nishiyama Noboru
- Japan Atomic Power Company (JAPC)
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- Uzawa Masayuki
- Mitsubishi FBR Systems, Inc. (MFBR)
抄録
Maintenance and repair program and conformity with them were investigated as a part of the conceptual design study of Japan Sodium-cooled Fast Reactor (JSFR). The maintenance program was set by taking the feature of sodium-cooled reactors and domestic practice of LWRs into account. Both of regulatory required inspection and voluntary inspection, which are conducted in the domestic LWRs, were counted. The regulatory required ISI program was based on that of the previous Japanese SFRs, LWRs (JSME S NA1) and liquid metal cooled reactors (ASME section XI division 3). Parts to be inspected, methods of inspection were identified for major structures and components. Concerning the repair program, we set three levels of repair requirements based on estimated frequency of defect and failure during the plant life time. For level 1, which might be occur several times during the plant life time, it is required to be easily repaired in a short period. Access routes and working space are considered in the component design and its arrangement. For level 2, which might be unlikely to occur during the plant life time, it is required to check that the repair work is feasible in a practical time range. For level 3, which frequency is negligible small, repair is not taken into account but the feasibility was investigated. The plant design shall be done so that all of above mentioned inspection and repair can be conducted. It is desired to ensure accessibility for all of the coolant and cover gas boundaries and the internal structures in order to cope with unforeseen troubles. Access routes for the reactor vessel and its internal structures, piping, pumps and intermediate heat exchangers and steam generators were investigated. As the results of that, possible ways for implementation of the maintenance and repair were identified.
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2011.19 (0), _ICONE1943-_ICONE1943, 2011
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390282680857091712
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- NII論文ID
- 110009956977
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- ISSN
- 24242934
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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