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Crack Propagation in a First Way by Cyclic High Hrat Flux

Research Project

Project/Area Number 05680428
Research Category

Grant-in-Aid for General Scientific Research (C)

Allocation TypeSingle-year Grants
Research Field Nuclear fusion studies
Research InstitutionUniversity of Tsukuba

Principal Investigator

SAITO Masakatsu  Univ.of Tsukuba, Inst.of Engng Mech, Professor, 構造工学系, 教授 (70029198)

Project Period (FY) 1993 – 1994
Project Status Completed (Fiscal Year 1994)
Budget Amount *help
¥2,000,000 (Direct Cost: ¥2,000,000)
Fiscal Year 1994: ¥800,000 (Direct Cost: ¥800,000)
Fiscal Year 1993: ¥1,200,000 (Direct Cost: ¥1,200,000)
Keywordsfusion reactor / first wall / crack growth / high heat flux / 電子ビーム照射 / J積分
Research Abstract

A 3 mm thick plate with a precrack is taken as a simple model of the first wall of the nuclear fusion reactor. To simulate the crack growth, high heat flux of 3MW/m2 is radiated to a circular area of 12 mm in diameter. Electron Beam is used as a heat source. 0.5 sec irradiation and 29.5 sec cooling is one cycle. The crack growth DELTAa is measured with respect to the cyclic number of heat irradiation. Average tensile stress of 50Mpa, 100MPa and 150MPa are loaded to the specimen in order to clarify the effects of the boundary condition. Finite element code ABAQUS is used for transient heat coduction analysis and elastoplastic stree analisys. The nonlinear fracture mechanics parameter J is numerically evaluated. Thus we have DELTAa/DELTAN (N : cyclic number) -DELTAJ relation.
In case of the average stress of 0MPa, (which is a result of the last year) 50MPa and 100MPa, the crack tip is yielded in compression by heat irradiation and is yieled in tesion by cooling. The rapid change of stress at crack tip make the crack to grow. This behavior is estimated by the above numrical model. But in case of the average stress 150MPa, the yield in compression does not appear by heat irradiation. The crack propagation behavior is similar to the conventional high temperature fatige test. This means that another model for culculation is needed to estimate the crack growth in the high average stress range.

Report

(3 results)
  • 1994 Annual Research Report   Final Research Report Summary
  • 1993 Annual Research Report
  • Research Products

    (9 results)

All Other

All Publications (9 results)

  • [Publications] T. Nishimura et. al: "Numerical analysis of crack propagation in a first wall by cyclic high heat flux irradiation" Proc. 18th Symposium on Fusion Technology, karlsruher. Aug. 1994.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] 西村俊則他: "第一壁の繰返し熱負荷による亀裂進展" 日本原子力学会1994年秋の大会予稿集II. 140-

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] 菅谷彰人他: "第一壁の繰返し熱負荷による亀裂進展" 日本原子力学会1995年春の年会要旨集.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] T.Nishimura et al: "Numerical analysis of crack propagation in a first wall by cyclic high heat flux irradiation" Proc.18th symposium on Fusion Technology Karlsruher, Arg.(1994)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] T.Nishimura et al: "Crack Propagation in a First Wall by cyclic High Heat Flux Irradiation" Preprint of Fall meating Atomic Energy Soc.of Jpn.II. 140 (1994)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] A.Sugaya et al: "Crack Propagation in a First Wall by Cyclic High Heat Flux Irradiation" Preprint of Spring Meating Atomic Energy Soc.of Jpn.(1995)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1994 Final Research Report Summary
  • [Publications] T.Nishimura et.al: "Numencal analysis of crack propegation in a first wall by cyclic high neat flux ivvadeation" Proc.18th Sympo.on Fusion Tech.Karlsruher,Ang.1994. (印刷中).

    • Related Report
      1994 Annual Research Report
  • [Publications] 西村俊則他: "第一壁の繰返し熱負荷による亀裂進展" 日本原子力学会 1994年秋の大会予稿集II. (印刷中). 140

    • Related Report
      1994 Annual Research Report
  • [Publications] 菅谷彰人他: "第一壁の繰返し熱負荷による亀裂進展" 日本原子力学会 1995年春の大会要旨集. (印刷中).

    • Related Report
      1994 Annual Research Report

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Published: 1993-04-01   Modified: 2016-04-21  

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