DEVELOPMENT OF THE EX-VESSEL MODULES FOR THE INTEGRATED SFR SAFETY ANALYSIS CODE SPECTRA
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- Aoyagi Mitsuhiro
- Japan Atomic Energy Agency
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- Makino Tohru
- NESI
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- Ohki Hiroshi
- NDD
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- Uchibori Akihiro
- Japan Atomic Energy Agency
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- Okano Yasushi
- Japan Atomic Energy Agency
説明
<p>The SPECTRA code has been developed as an integrated safety analysis tool for comprehensive analyses of in- and ex-vessel phenomena during a severe accident (SA) in a sodium-cooled fast reactor (SFR). The individual modules, such as sodium fire and sodium-concrete reaction, have been implemented into SPECTRA to simulate specific phenomena in an accident of SFRs. However, SPECTRA has no capability for the overlapped event involving sodium fire and sodium-concrete reaction because the sodium pool and the floor concrete are modeled in each module independently. In this study, the capability of SPECTRA is enhanced by integrating the analyses of sodium pool fire and concrete ablation for overlapped events of the ex-vessel phenomena. The sodium pool fire module is connected to the shared module for the sodium pool and the floor concrete developed in our previous study. The developed model is validated through the benchmark analysis of the F7-1 pool fire experiment. The calculation result of the pool and catch pan temperature shows good agreement with the experimental data. A demonstration analysis is also conducted for an overlapped event of the ex-vessel phenomena. SPECTRA can simulate a reasonable heat and mass transfer behavior.</p>
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 2023.30 (0), 1342-, 2023
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
- 1390298278366401408
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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
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- 抄録ライセンスフラグ
- 使用不可