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- Yoshida Kohei
- Hitachi-GE Nuclear Energy, Ltd.
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- Ishiwatari Yuki
- Hitachi-GE Nuclear Energy, Ltd.
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- Shiota Daichi
- Hitachi-GE Nuclear Energy, Ltd.
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- Echizen Kyohei
- Hitachi Industry & Control Solutions, Ltd.
抄録
Loss of Coolant Accidents (LOCAs) inside and outside containment are typical initiating events considered in Probabilistic Safety Assessment (PSA). The LOCA events on individual lines are grouped by similar success criteria including availability of the mitigation systems. While keeping the total LOCA frequency unchanged, there could be two approaches to the LOCA modeling in PSA: (1) a LOCA event on each line is represented by guillotine break, or (2) partial fracture(s) is separately considered from guillotine break (e.g., Small and Medium LOCAs caused by cracks or hole on pipes of larger size with different success criteria). In this paper, the modelling uncertainty associated with the relatively simplified approach (1) is characterized by sensitivity analyses based on the detailed approach (2), using the ABWR (Advanced Boiling Water Reactor) PSA. LOCAs inside containment are analyzed by the internal events at power PSA while LOCAs outside containment are analyzed by the internal flooding at power PSA.
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 2019.27 (0), 1150-, 2019
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
- 1390846609786833408
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- NII論文ID
- 130007773414
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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