2023 Fiscal Year Final Research Report
Development of Super Fast Reactor for Post Severe Accident Management
| Project/Area Number |
20H02669
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Single-year Grants |
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| Section | 一般 |
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| Review Section |
Basic Section 31010:Nuclear engineering-related
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| Research Institution | Waseda University |
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Principal Investigator |
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| Project Period (FY) |
2020-04-01 – 2024-03-31
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| Keywords | 超臨界圧軽水冷却炉 / スーパー高速炉 / 原子炉過酷事故解析 / In-Vessel Retention / 炉心設計 / MELCORコード / MPS法 / マルチフィジックス |
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| Outline of Final Research Achievements |
Post severe accident management concept of supercritical water-cooled fast reactor (Super FR) has been developed with multi-physics modeling, covering the core neutronics, thermal-hydraulics, the plant safety analyses and the molten core material behavior analyses. It was anticipated that due to the low boiling point of water under atmospheric pressure, the entire core would melt down and relocate to the bottom of the Reactor Pressure Vessel (RPV). A new concept to avoid re-criticality has been developed through core design and criticality evaluation of the fuel debris. Comprehensive relationships between the core design parameters, the core performance and the debris re-criticality has been clarified. New research issues of MPS method for crust modeling has also been identified with a possible solution.
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| Free Research Field |
原子炉の炉心設計、プラント安全解析、過酷事故
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| Academic Significance and Societal Importance of the Research Achievements |
原子炉の社会的受容性を改善するには「炉心損傷確率や放射性物質の放出確率の低減、過酷事故の実質的な回避（practically eliminate）や発電所周辺住民の避難を不要とする設計（evacuation free）の考え方に基づく、原子炉の事故耐性の向上だけでは不十分であることに着目し、新たな考え方として設計段階から過酷事故終息後を見据えた研究に取り組み、事故終息時の炉内状況を概念的に設計に盛り込むことができる可能性を示した。
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