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Behavior of nuclear reactor materials at high damage levels investigated by ion-irradiation and point defect reaction models

Research Project

Project/Area Number 23561022
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeMulti-year Fund
Section一般
Research Field Nuclear engineering
Research InstitutionFukushima National College of Technology (2012-2014)
Japan Atomic Energy Agency (2011)

Principal Investigator

JITSUKAWA Shiro  福島工業高等専門学校, その他部局等, 教授 (80354835)

Co-Investigator(Renkei-kenkyūsha) OKUBO Nariaki  独)日本原子力研究開発機構, 研究副主幹 (60391330)
ABE Yosuke  独)日本原子力研究開発機構, 研究員 (50400403)
Project Period (FY) 2011-04-28 – 2015-03-31
Project Status Completed (Fiscal Year 2014)
Budget Amount *help
¥4,810,000 (Direct Cost: ¥3,700,000、Indirect Cost: ¥1,110,000)
Fiscal Year 2013: ¥910,000 (Direct Cost: ¥700,000、Indirect Cost: ¥210,000)
Fiscal Year 2012: ¥1,820,000 (Direct Cost: ¥1,400,000、Indirect Cost: ¥420,000)
Fiscal Year 2011: ¥2,080,000 (Direct Cost: ¥1,600,000、Indirect Cost: ¥480,000)
Keywords原子力エネルギー / 構造・機能材料 / 格子欠陥 / 加速器 / モデル化 / 照射損傷 / 微細組織 / 硬化 / 金属物性 / 原子炉材料 / 核融合炉材料 / 中性子照射 / 照射硬化 / 照射脆化 / イオン照射 / 弾き出し損傷 / ヘリウム脆性 / 核変換生成ヘリウム原子
Outline of Final Research Achievements

High-energy neutrons introduce displacement damages and transmutation produced impurity atoms (e.g. He atoms) in nuclear reactor materials. Irradiation with Fe and He ions on austenitic and martensitic steels to damage levels of 200 dpa and 20000 appm have been carried out to investigate the effect of temperature on the damage level dependence of hardening and reduction of toughness. Below 100oC, specimens exhibited hardening well below 0.1 dpa. However, the damage levels of hardening increased with temperature to 1 dpa level at 400oC. He atoms also introduce additional hardening with about <1000 appm and <10000appm for martensitic and austenitic steels, respectively. The displacement damage level dependence of hardness of austenitic steels seems to be modeled by rate theory with capture radius concept of dislocations for the point defects and small defect clusters. By using the model, a method to estimate stress-strain relations as a function of damage level has been also developed.

Report

(5 results)
  • 2014 Annual Research Report   Final Research Report ( PDF )
  • 2013 Research-status Report
  • 2012 Research-status Report
  • 2011 Research-status Report
  • Research Products

    (8 results)

All 2013 2012 2011

All Journal Article (5 results) (of which Peer Reviewed: 4 results) Presentation (3 results)

  • [Journal Article] Development of Models for Irradiation-induced Changes to Microstructure and Stress–Strain Relations of Austenitic Steels2013

    • Author(s)
      S. Jitsukawa, Y. Abe, K. Suzuki and N. Okubo
    • Journal Title

      Effects of Radiation on Nuclear Materials

      Volume: ASTM STP 1547 Pages: 288-312

    • DOI

      10.1520/stp104147

    • ISBN
      9780803175334, 9780803175631
    • Related Report
      2013 Research-status Report 2012 Research-status Report
    • Peer Reviewed
  • [Journal Article] Cluster Dynamics Simulation on Microstructure Evolution of Austenitic Stainless Steel and alpha-Iron Under Cascade Damage Condition2012

    • Author(s)
      Y. Abe, S. Jitsukawa, N. Okubo, H. Matsui and T. Tsukada
    • Journal Title

      Effects of Radiation on Nuclear Materials

      Volume: ASTM STP 1547 Pages: 313-337

    • DOI

      10.1520/stp103991

    • ISBN
      9780803175334, 9780803175631
    • Related Report
      2013 Research-status Report 2012 Research-status Report
    • Peer Reviewed
  • [Journal Article] Effects of carbon impurity on microstructural evolution in irradiated alpha-iron2012

    • Author(s)
      Y. Abe, T. Suzudo and S. Jitsukawa
    • Journal Title

      Fusion Science and Technology

      Volume: 62 Pages: 139-144

    • Related Report
      2012 Research-status Report
    • Peer Reviewed
  • [Journal Article] Heat treatment effect on fracture toughness of F82H irradiated in HFIR2011

    • Author(s)
      N. Okubo, M.A. Sokolov, H. Tanigawa, T. Hirose, S. Jitsukawa他
    • Journal Title

      Journal of Nuclear Materials

      Volume: 417 Pages: 112-114

    • Related Report
      2011 Research-status Report
    • Peer Reviewed
  • [Journal Article] Micro-structure and micro-hardness of ODS steels after ion irradiation2011

    • Author(s)
      C. Liu, C. Yu, N. Hashimoto, S. Ohnuki, M. Ando, K. Shiba, S. Jitsukawa
    • Journal Title

      Journal of Nuclear Materials

      Volume: 417 Pages: 270-273

    • Related Report
      2011 Research-status Report
  • [Presentation] Mechanical response of martensitic and austenitic steels after ion-irradiation to very high damage levels2013

    • Author(s)
      Shiro Jitsukawa
    • Organizer
      16th International conference on fusion reactor materials
    • Place of Presentation
      Beijing, China
    • Related Report
      2013 Research-status Report
  • [Presentation] Development of models for irradiation-induced changes to microstructure and stress-strain relations of austenitic steels2011

    • Author(s)
      S. Jitsukawa, Y. Abe 他
    • Organizer
      25th Symposium on Effects of radiation on nuclear materials, American Society for Testing and Materials
    • Place of Presentation
      米国 カリフォルニア州 アナハイム
    • Related Report
      2011 Research-status Report
  • [Presentation] Preliminary models on irradiation induced changes of microstructure and stress-strain relations to estimate mechanical response of the components of fusion machines with reduced activation ferritic steels2011

    • Author(s)
      S. Jitsukawa, Y. Abe 他
    • Organizer
      15th International Conference on Fusion Reactor Materials
    • Place of Presentation
      米国 バージニア州 チャールストン
    • Related Report
      2011 Research-status Report

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Published: 2011-08-05   Modified: 2019-07-29  

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