ICONE19-43594 Conceptual Design Study for the Demonstration Reactor of JSFR : (3) Safety Design and Evaluation
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- Tani Akihiro
- Mitsubishi FBR Systems, INC (MFBR)
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- Shimakawa Yoshio
- Mitsubishi FBR Systems, INC (MFBR)
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- Kubo Shigenobu
- Mitsubishi FBR Systems, INC (MFBR)
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- Fujimura Ken
- Japan Atomic Energy Agency (JAEA)
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- Yamano Hidemasa
- Japan Atomic Energy Agency (JAEA)
抄録
This paper describes the result of conceptual safety design and evaluation for the demonstration plant of Japan sodium-cooled fast reactor (JSFR), which was preliminarily conducted for providing information necessary to decide the plant specification for further design study. The plant major specifications except for output power and safety design concept are almost the same as those of the commercial JSFR. A set of safety evaluation for typical design basis events (DBEs) is mainly focused here, which was conducted for the 750 MWe design. Safety analyses for DBEs evaluation were performed on the basis of conservative assumptions using a one-dimensional flow network code with point kinetics. For representative DBEs, transient over power type events and loss of flow type events were analyzed. The long-term loss-of-offsite power event was also calculated to evaluate the natural circulation decay heat removal system. All analytical results showed to meet tentative safety criteria, thus it was confirmed that the safety design concept of JSFR is feasible against DBEs.
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
- 1390001205880381440
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- NII論文ID
- 110009956976
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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