2022 Fiscal Year Final Research Report
Development of the Innovative Passive Safety System for Next Generation Nuclear Reactors
Project/Area Number |
19H02638
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Research Category |
Grant-in-Aid for Scientific Research (B)
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Allocation Type | Single-year Grants |
Section | 一般 |
Review Section |
Basic Section 31010:Nuclear engineering-related
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Research Institution | The University of Tokyo (2020-2022) Hokkaido University (2019) |
Principal Investigator |
Miwa Shuichiro 東京大学, 大学院工学系研究科(工学部), 准教授 (00705288)
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Co-Investigator(Kenkyū-buntansha) |
坂下 弘人 北海道大学, 工学研究院, 特任教授 (00142696)
伊藤 大介 京都大学, 複合原子力科学研究所, 助教 (30630024)
伊藤 啓 京都大学, 複合原子力科学研究所, 准教授 (50421590)
舩谷 俊平 山梨大学, 大学院総合研究部, 准教授 (50607588)
沢 和弘 北海道大学, 工学研究院, 教授 (80355015)
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Project Period (FY) |
2019-04-01 – 2022-03-31
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Keywords | 気液二相流 / 蒸気インジェクタ |
Outline of Final Research Achievements |
The following is a summary of the Steam Injector (SI) experiments and analytical models conducted under this funding period. Regarding the operation characteristics of the SI, it was suggested that as the supply steam pressure increases, a water jet is formed in the mixing nozzle, and that its length is proportional to the steam pressure. After the SI internal pressure was increased by adjusting the back pressure valve, it was confirmed that a condensation shock was formed at the rear part of the diffuser. The one-dimensional model newly developed through this research grant can calculate the pressure distribution of the SI more accurately than conventional methods. By incorporating the newly proposed condensation shock model into the momentum conservation equation as an additional term, it was confirmed that the accuracy of the calculated maximum discharge pressure was greatly improved.
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Free Research Field |
熱流動工学
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Academic Significance and Societal Importance of the Research Achievements |
SIは、蒸気の熱エネルギーを運動エネルギーに変換することで、入口蒸気圧力よりも常に高い吐出圧が得られる装置である。SIを静的安全装置の一部として原子力施設へ導入することで、事故時に発生する蒸気を利用し、水噴流と混合させることで、圧力変動に影響されずに安定した注水と徐熱が可能となる。更に、混合ノズル内部において生じる蒸気-水の直接接触凝縮型熱交換は、従来の熱交換機の1,000倍以上の伝熱性能を有する。本研究成果は小型炉等の次世代原子炉へのSI導入に向けて必要となる最大吐出圧ならびに正常作動・不作動の作動条件を熱流体工学の観点から検証したものであり、次世代炉の安全性向上に寄与するものと期待される。
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