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Development of Advanced Steels for Irradiation Environment

Research Project

Project/Area Number 09045042
Research Category

Grant-in-Aid for international Scientific Research

Allocation TypeSingle-year Grants
SectionUniversity-to-University Cooperative Research
Research Field Nuclear fusion studies
Research InstitutionHOKKAIDO UNIVERSITY

Principal Investigator

TAKAHASHI Heishichiro  Hokkaido University, Center for Advanced Research of Energy Technology, Professor, エネルギー先端工学研究センター, 教授 (80001337)

Co-Investigator(Kenkyū-buntansha) 万 発栄  北京科技大学材料系, 教授
胡 本芙  北京科技大学材料系, 教授
KINOSHITA Hiroshi  Hokkaido Univ.Center for Advanced Res.of Energy Tech.Assistant, エネルギー先端工学研究センター, 助手 (40177895)
SHIBAYAMA Tamaki  Hokkaido Univ.Center for Advanced Res.of Energy Tech.Assistant, エネルギー先端工学研究センター, 助手 (10241564)
HU Benfu  University of Science & Tech.Beijing, Dep.of Maters., Professor
WAN Farong  University of Science & Tech.Beijing, Dep.of Maters., Professor
渡辺 精一  北海道大学, 大学院・工学研究科, 助教授 (60241353)
Project Period (FY) 1997 – 1998
Project Status Completed (Fiscal Year 1998)
Budget Amount *help
¥1,900,000 (Direct Cost: ¥1,900,000)
Fiscal Year 1998: ¥900,000 (Direct Cost: ¥900,000)
Fiscal Year 1997: ¥1,000,000 (Direct Cost: ¥1,000,000)
Keywordshigh Mn steel / lower radioactivity / fusion reactor / electron-irradiation / radiation-damage / He effect / mechanical properties / void swelling / 相不安定性 / ボイドフェリング
Research Abstract

1. When 316 stainless steel was electron-irradiated, stacking fault dislocation loops were nucleated, and then finally stacking fault tetrahedra of vacancy type (SFT) were nucleated inside the loops. These SFTs acted as void nucleation sites under electron/He dual irradiation.
2. Fe-(15-16)% Cr-16% Mn-O.2% C-O.2% N steels have yield stress of 400 MPa and the elongation of 60% at room temperature. These high Mn steels showed excellent irradiation-resistance under irradiation.
3. When Fe-Cr-Mn(W,V) steels with W and V were irradiated, no segregation was recognized, and then it was suggested that by adding W, and V segregation is retarded.
4. The same Fe-Cr-Mn containing W and V showed higher resistance for irradiation at
625K but at higher temperature a lot of small voids were nucleated.
5. In Fe-Cr-Mn steels the segregation at grain boundary was larger than the steel with W and V.
6.lt was clarified for Fe-(13-16) Cr-(6.5-24.5) Mn-(0.02-0.2)C-0.2 N steels that (a) by contorolling the composition of Cr, C,N single phase of austenite can be obtained even for lower Mn concentration steels, (b)Fe-(15-16)wt% Cr-15.5wt% Mn-(O.02-O.2)wt% C-0.2wt% N steels have excellent mechanical properties, and (c) voids formation were perfectly retarded for Fe-l6wt% Cr-15.5wt% Mn-O.2wt% C-O.2wt% N steel under irradiation at 473-673K.

Report

(3 results)
  • 1998 Annual Research Report   Final Research Report Summary
  • 1997 Annual Research Report
  • Research Products

    (23 results)

All Other

All Publications (23 results)

  • [Publications] 高橋平七郎: "オーステナイト相安定型低放射化高マンガン鋼の機械的性質及び照射損傷挙動" 日本原子力学会1997年秋期論文集. 150-151 (1997)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 胡 本芙: "Damage Behavior of Oxide Dispersion Strengthened Ferritic Steel Under Dual-Beam Irradiation" The 4th Japan-China Symposium on Materials for Avanced Energy Systems and Fission and Fusion Engineering. 202-207 (1997)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 高橋平七郎: "Void formation and microstructural development in oxide dispersion strengthened ferritic steels during electron-irradiation" Journal Nuclear Materials. Vol.258/263. 1264-1268 (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 坂口紀史: "Effect of Additional Minor Element on Radiation-Induced Segregation in Austenitic Stanless Steel," Proc.of The 1998 Inter.Symp. on Advanced Energy Tech.639-642 (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 斉藤 順: "Mechanical properties and damage behavior of non-magnetic high manganese austenitic steels," Journal Nuclear Materials,. Vol.258/263. 1644-1650 (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 胡 本芙: "Damage Behavior in an electron/helium dual irradiated Fe-Cr-Mn(W,V) alloy of Oxide Dispersion Strengthened" Journal Nuclear Materials,. Vol.258/263. 1708-1712 (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 胡 本芙: "Irradiation Damage of Oxide Dispersion Strengthened Ferritic Steel after Recrystallization" Journal of University of Science & Technology Beijing,. Vol.5. 160-164 (1998)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] H.Takahashi: "Mechanical Properties and Irradiation Damage Behavior of Lower Activeted High Mn Austenitic Steels" Proc.of 1997 Fall Meeting of Japan Atomic Energy Society. 150-151 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] Hu Benfu: "Damage Behavior of Oxide Dispersion Strengthened Ferritic Steel Under Dual-Beam Irradiation" The 4th Japan-China Symposium on Materials for Avanced Energy Systems and Fission and Fusion Engineering. 202-207 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] H.Takahashi: "Void formation and microstructural development in oxide dispersion strengthened ferritic steels during electron-irradiation" Journal Nuclear Materials. Vol.258/263. 1264-1268 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] N.Sakaguchi: "Effect of Additional Minor Element on Radiation -Induced Segregation in Austenitic Stanless Steel" Proc.of The 1998 Inter.Symp.on Advanced Energy Tech.639-642 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] J.Saito: "Mechanical properties and damage behavior of non-magnetic high manganese austenitic steels" Journal Nuclear Materials. Vol.258/263. 1644-1650 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] H.Benfu: "Damage Behavior in an electron/helium dual irradiated Fe-Cr-Mn (W,V) alloy of Oxide Dispersion Strengthened steels" Journal Nuclear Materials. Vol.258/263. 1708-1712 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] H.Benfu: "Irradiation Damage of Oxide Dispersion Strengthened Ferritic Steel after Recrystallization" Journal of University of Science & Tech.Beijing. Vol.5. 160-164 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1998 Final Research Report Summary
  • [Publications] 高橋平七郎: "Void formation and microstructural development in oxide dispersion strengthened ferritic steels during electron-irradiation" Journal Nuclear Materials. 258/263. 1264-1268 (1998)

    • Related Report
      1998 Annual Research Report
  • [Publications] 坂口紀史: "Effect of Additional Minor Element on Radiation-Induced Segregation in Austenitic Stanless Steel." Proc.of The 1998 Inter.Symp.on Advanced Energy Tech.639-642 (1998)

    • Related Report
      1998 Annual Research Report
  • [Publications] 斉藤 順: "Mechanical properties and damage behavior of non-magnetic high manganese austenitic steels." Journal Nuclear Materials. 258/263. 1644-1650 (1998)

    • Related Report
      1998 Annual Research Report
  • [Publications] 胡本芙: "Damage Behavior in an electron/helium dual irradiated Fe-Cr-Mn(W,V)alloy of Oxide Dispersion Strengthened" Journal Nuclear Materials. 258/263. 1708-1712 (1998)

    • Related Report
      1998 Annual Research Report
  • [Publications] 胡本芙: "Irradiation Damage of oxide Dispersion Strengthened Ferritic Steel after Recrystallizatioin" Jouranl of University of Science & Technology Beijing. 5. 160-164 (1998)

    • Related Report
      1998 Annual Research Report
  • [Publications] 高橋 平七郎: "オーステナイト相安定型低放射化高マンガン鋼の機械的性質及び照射損傷挙動" 日本原子力学会1997年秋期大会論文集. 150-151 (1997)

    • Related Report
      1997 Annual Research Report
  • [Publications] 胡本芙: "Damage Behavior of Oxide Dispersion Strengthened Ferritic Steel Under Dual-Beam Irradiation" The 4th Japan-China Symposium on Materials for Advanced Energy System and Fission and Fusion Engineering. 202-207 (1997)

    • Related Report
      1997 Annual Research Report
  • [Publications] 胡本芙: "Damage Behavior of Electron/Helium Dual Beam Irradiated Fe-Cr-Mn (W.V) Alloys" J.Nuclear Matterials. (予定). (1998)

    • Related Report
      1997 Annual Research Report
  • [Publications] 高橋 平七郎: "Mechanical Properties and Damage Behaviors of Nonmagnetic High Manganese Austenitic Steel" J.Nuclear Matterials. (予定). (1998)

    • Related Report
      1997 Annual Research Report

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Published: 1997-04-01   Modified: 2016-04-21  

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