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Fusion reactor concept with high social acceptance through a radioactive waste management strategy

Research Project

Project/Area Number 18K03595
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeMulti-year Fund
Section一般
Review Section Basic Section 14020:Nuclear fusion-related
Research InstitutionNational Institutes for Quantum Science and Technology

Principal Investigator

SOMEYA Youji  国立研究開発法人量子科学技術研究開発機構, 六ヶ所研究所 核融合炉システム研究開発部, 主幹研究員 (20589345)

Project Period (FY) 2018-04-01 – 2023-03-31
Project Status Completed (Fiscal Year 2022)
Budget Amount *help
¥2,730,000 (Direct Cost: ¥2,100,000、Indirect Cost: ¥630,000)
Fiscal Year 2020: ¥650,000 (Direct Cost: ¥500,000、Indirect Cost: ¥150,000)
Fiscal Year 2019: ¥650,000 (Direct Cost: ¥500,000、Indirect Cost: ¥150,000)
Fiscal Year 2018: ¥1,430,000 (Direct Cost: ¥1,100,000、Indirect Cost: ¥330,000)
Keywords核融合炉 / 原型炉 / 放射性廃棄物 / 減容化 / リサイクル / 核融合原型炉 / 廃棄物管理 / 再利用 / トリチウムインベントリ / 埋設区分
Outline of Final Research Achievements

The management strategy for reducing the radioactive waste (radwaste) generated by the replacement of the in-vessel components (IVCs) was considered, and it was found that radwaste could be reduced to 60 % when a back-plate and divertor cassette with low neutron irradiation are reused and the T breeding materials are recycled. The blanket first wall, which is the maximum radioactivity concentration, can be recycled by remote equipment after being stored for 100 years, and the amount of radwaste generated can be also greatly reduced. In addition, the tritium inventory of spent IVCs is expected to prevent inadvertent diffusion by controlling the temperature of IVCs that are heated by the residual heat, thereby reducing radwaste exposed to tritium generated by buildings.

Academic Significance and Societal Importance of the Research Achievements

本研究は核融合炉のプラントライフ中に発生する放射化物の中で、大量で高い放射能濃度を有する定期交換時に発生する放射化物に着目し、当該放射化物の核特性(誘導放射能濃度、表面線量率、残留熱)の理解に基づく再利用やリサイクルによる減容化戦略により、社会受容性が高い核融合炉に資する成果といえる。

Report

(6 results)
  • 2022 Annual Research Report   Final Research Report ( PDF )
  • 2021 Research-status Report
  • 2020 Research-status Report
  • 2019 Research-status Report
  • 2018 Research-status Report
  • Research Products

    (11 results)

All 2023 2022 2021 2020 2019 2018

All Presentation (11 results) (of which Invited: 3 results)

  • [Presentation] Radwaste management scenarioon fusion DEMO plants in Japan2023

    • Author(s)
      SOMEYA Youji
    • Organizer
      Technical Meeting on Decommissioning Considerations for Fusion Facilities (IAEA)
    • Related Report
      2022 Annual Research Report
  • [Presentation] 原型炉における安全設計研究の現状2022

    • Author(s)
      染谷洋二、加藤満也、中村博文、古谷正裕、川崎大介、坂本宜照
    • Organizer
      第39回 プラズマ・核融合学会 年会
    • Related Report
      2022 Annual Research Report
  • [Presentation] MANAGEMENT STRATEGY ON RADIOACTIVE WASTE OF FUSION DEMO REACTOR OF JAPAN2021

    • Author(s)
      Someya Youji, Tobita Kenji, Sakamoto Yoshiteru, Hiwatari Ryoji
    • Organizer
      Workshop on Waste Management for Fusion (IAEA)
    • Related Report
      2021 Research-status Report
    • Invited
  • [Presentation] Progress of conceptual design and key engineering issues on JA DEMO2021

    • Author(s)
      Someya Youji, Sakamoto Yoshiteru, Hiwatari Ryoji, Aiba Nobuyuki, Uto Hiroyasu
    • Organizer
      The 30th International Toki Conference on Plasma and Fusion Research
    • Related Report
      2021 Research-status Report
    • Invited
  • [Presentation] 原型炉の安全確保に向けた安全設計研究の現状2021

    • Author(s)
      染谷洋二、加藤満也 、坂本宜照 、日渡良爾
    • Organizer
      第38回 プラズマ・核融合学会 年会
    • Related Report
      2021 Research-status Report
  • [Presentation] オーガナイズドセッション(トリチウム):原型炉トリチウムインベントリ評価に向けて2020

    • Author(s)
      染谷洋二、岩井保則、大矢恭久、波多野雄治、片山一成、芦川直子、鳥養祐二、日渡良爾、坂本宜照、原型炉設計合同特別チーム
    • Organizer
      プラズマ・核融合学会 37回年会
    • Related Report
      2020 Research-status Report
  • [Presentation] 原型炉プラントの安全確保に向けた安全設計研究の進捗2020

    • Author(s)
      染谷洋二、加藤満也、陳偉熙、日渡良爾、坂本宜照、原型炉設計合同特別チーム
    • Organizer
      プラズマ・核融合学会 37回年会
    • Related Report
      2020 Research-status Report
  • [Presentation] 核融合原型炉の概念設計の進展2019

    • Author(s)
      染谷洋二、坂本宜照、日渡良爾、相羽信行、中島徳嘉、宇藤裕康、飛田健次
    • Organizer
      プラズマ・核融合学会 第36回年会
    • Related Report
      2019 Research-status Report
    • Invited
  • [Presentation] 炉内トリチウムインベントリの評価に向けて2019

    • Author(s)
      染谷洋二
    • Organizer
      プラズマ・核融合学会 第36回年会
    • Related Report
      2019 Research-status Report
  • [Presentation] 原型炉プラントの安全確保に向けた安全設計活動2018

    • Author(s)
      染谷洋二、中村誠、三善悠矢、宇藤裕康、角舘聡、日渡良爾、坂本宜照、飛田健次
    • Organizer
      第12回核融合エネルギー連合講演会
    • Related Report
      2018 Research-status Report
  • [Presentation] 原型炉プラントの安全確保に向けた安全設計の進展2018

    • Author(s)
      染谷洋二、加藤満也、日渡良爾、坂本宜照、飛田健次
    • Organizer
      第35回プラズマ・核融合学会年会
    • Related Report
      2018 Research-status Report

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Published: 2018-04-23   Modified: 2024-01-30  

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