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Development of Super Fast Reactor for Post Severe Accident Management

Research Project

Project/Area Number 20H02669
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Review Section Basic Section 31010:Nuclear engineering-related
Research InstitutionWaseda University

Principal Investigator

Yamaji Akifumi  早稲田大学, 理工学術院, 教授 (00571704)

Project Period (FY) 2020-04-01 – 2024-03-31
Project Status Completed (Fiscal Year 2023)
Budget Amount *help
¥8,840,000 (Direct Cost: ¥6,800,000、Indirect Cost: ¥2,040,000)
Fiscal Year 2023: ¥2,470,000 (Direct Cost: ¥1,900,000、Indirect Cost: ¥570,000)
Fiscal Year 2022: ¥2,210,000 (Direct Cost: ¥1,700,000、Indirect Cost: ¥510,000)
Fiscal Year 2021: ¥2,210,000 (Direct Cost: ¥1,700,000、Indirect Cost: ¥510,000)
Fiscal Year 2020: ¥1,950,000 (Direct Cost: ¥1,500,000、Indirect Cost: ¥450,000)
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 / 小型炉 / 過酷事故解析
Outline of Research at the Start

従来の原子炉の安全研究は究極の安全性を追求するのみだが、それでは絶対安全を求める社会とのギャップを永遠に埋められない可能性がある。そこで、本研究では簡素でコンパクトな貫流直接サイクルを採用する超臨界圧軽水冷却スーパー高速炉を対象に、万が一の事故時には全炉心がメルトダウンし、RPV底部に移行することを前提にする。その上で、RPV内部に燃料デブリを留め、その再臨界を回避して安定冷却を達成する(福島事故のようなデブリの炉外への流出を起こさない)、新しい事故復旧性小型スーパー高速炉の概念を創出することを目的とする。

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.

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。

Report

(5 results)
  • 2023 Annual Research Report   Final Research Report ( PDF )
  • 2022 Annual Research Report
  • 2021 Annual Research Report
  • 2020 Annual Research Report
  • Research Products

    (17 results)

All 2024 2023 2022 2021 2020

All Journal Article (7 results) (of which Int'l Joint Research: 1 results,  Peer Reviewed: 5 results) Presentation (10 results) (of which Int'l Joint Research: 6 results)

  • [Journal Article] Scope of conceptual development of Resilient supercritical Light water-cooled reactor (SCWR-R)2024

    • Author(s)
      Yamaji Akifumi、Matsuoka Koki、Sumida Kota、Funatsu Kohki
    • Journal Title

      Nuclear Engineering and Design

      Volume: 416 Pages: 112756-112756

    • DOI

      10.1016/j.nucengdes.2023.112756

    • Related Report
      2023 Annual Research Report
    • Peer Reviewed
  • [Journal Article] A new potential interface tension model for MPS method avoiding unphysical particle cohesion2022

    • Author(s)
      Fukuda Takanari、Li Xin、Yamaji Akifumi
    • Journal Title

      Progress in Nuclear Energy

      Volume: 150 Pages: 104311-104311

    • DOI

      10.1016/j.pnucene.2022.104311

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed
  • [Journal Article] 2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model2021

    • Author(s)
      Jubaidah、Umazume Yuki、Takahashi Nozomu、Li Xin、Duan Guangtao、Yamaji Akifumi
    • Journal Title

      Nuclear Engineering and Design

      Volume: 379 Pages: 111251-111251

    • DOI

      10.1016/j.nucengdes.2021.111251

    • Related Report
      2021 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 32021

    • Author(s)
      Takahashi Nozomu、Duan Guangtao、Yamaji Akifumi、Li Xin、Sato Ikken
    • Journal Title

      Nuclear Engineering and Design

      Volume: 379 Pages: 111244-111244

    • DOI

      10.1016/j.nucengdes.2021.111244

    • Related Report
      2021 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Improvement of solidification model and analysis of 3D channel blockage with MPS method2021

    • Author(s)
      Kawakami Reo、Li Xin、Duan Guangtao、Yamaji Akifumi、Sato Isamu、Suzuki Tohru
    • Journal Title

      Frontiers in Energy

      Volume: 15 Issue: 4 Pages: 946-958

    • DOI

      10.1007/s11708-021-0754-z

    • Related Report
      2021 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Preliminary Core Design Study of Small Supercritical Fast Reactor with Single-Pass Cooling2020

    • Author(s)
      Uchimura Kyota、Yamaji Akifumi
    • Journal Title

      Journal of Nuclear Engineering

      Volume: 1 Issue: 1 Pages: 46-53

    • DOI

      10.3390/jne1010004

    • Related Report
      2020 Annual Research Report
  • [Journal Article] Conceptual design of Super FR for MA transmutation with axially heterogeneous core2020

    • Author(s)
      Fukuda Takanari、Yamaji Akifumi
    • Journal Title

      Nuclear Engineering and Design

      Volume: 363 Pages: 110619-110619

    • DOI

      10.1016/j.nucengdes.2020.110619

    • Related Report
      2020 Annual Research Report
  • [Presentation] Preliminary Conceptual Development of the Super LWR Spectral Shift Core2023

    • Author(s)
      Akira Hirose; Takanari Fukuda; Akifumi Yamaji
    • Organizer
      30th International Conference on Nuclear Engineering(ICONE30)
    • Related Report
      2023 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Investigation of the Plant Characteristics and Management of Super-FR during BDBA-LOCA2022

    • Author(s)
      Kota Sumida, Akifumi Yamaji
    • Organizer
      13th International Topical Meeting on Nuclear Reactor Thermal- Hydraulics Operation and Safety(NUTHOS-13)
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Analysis of Molten Metal Flow and Freezing in a 3-D Pin Bundle Geometry by MPS Method2022

    • Author(s)
      Haruki Takei, Takanari Fukuda, Xin Li, Akifumi Yamaji
    • Organizer
      13th International Topical Meeting on Nuclear Reactor Thermal- Hydraulics Operation and Safety(NUTHOS-13)
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Three-Dimensional Analyses of the FARO L-26S Melt Spreading Experiment by MPS Method2022

    • Author(s)
      Sara Honda,Takanari Fukuda, Guangtao Duan, and Akifumi Yamaji,
    • Organizer
      13th International Topical Meeting on Nuclear Reactor Thermal- Hydraulics Operation and Safety(NUTHOS-13)
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Evaluation of Thermal Load on the BWR Containment With Different Depressurization Timings During Loss of Core Cooling Severe Accidents2022

    • Author(s)
      Taisei Matsumoto, Akifumi Yamaji , Daisuke Fujiwara
    • Organizer
      29th International Conference on Nuclear Engineering (ICONE29)
    • Related Report
      2022 Annual Research Report
  • [Presentation] Core design of SUPER FR-MIX for improving neutronics and thermal-hydraulics performances2021

    • Author(s)
      T.Horiguchi, A.Yamaji,T.Fukuda, K.Uchimura
    • Organizer
      The 10th International Symposium on Supercritical Water-Cooled Reactors
    • Related Report
      2020 Annual Research Report
    • Int'l Joint Research
  • [Presentation] LOCA analysis of super FR with RELAP/SCDAPSIM and FEMAXI-72021

    • Author(s)
      S.Nakamoto, A.Yamaji, T.Okui
    • Organizer
      The 10th International Symposium on Supercritical Water-Cooled Reactors
    • Related Report
      2020 Annual Research Report
    • Int'l Joint Research
  • [Presentation] VULCANO VF-U1実験における金属コリウム局所凝固挙動のMPS法による解析2021

    • Author(s)
      福田貴斉, 山路哲史, Li Xin
    • Organizer
      日本原子力学会春の年会
    • Related Report
      2020 Annual Research Report
  • [Presentation] 超臨界圧軽水冷却スーパー高速炉の炉心及び再臨界を回避するIVRの設計2021

    • Author(s)
      佐々木凌太郎,山路哲史
    • Organizer
      日本原子力学会関東・甲越支部第14回学生研究発表会
    • Related Report
      2020 Annual Research Report
  • [Presentation] MELCOR-2.2によるスーパー高速炉の設計基準を超えた冷却材喪失事故解析2021

    • Author(s)
      鈴木亨,山路哲史
    • Organizer
      日本原子力学会関東・甲越支部第14回学生研究発表会
    • Related Report
      2020 Annual Research Report

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Published: 2020-04-28   Modified: 2025-01-30  

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