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Evaluation of Creep-Fatigue-Environment Interaction Based on Mechanical Response

Research Project

Project/Area Number 61460085
Research Category

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

Allocation TypeSingle-year Grants
Research Field 材料力学
Research InstitutionUniversity of Tokyo

Principal Investigator

ASADA Yasuhide  Faculty of Engineering, University of Tokyo, 工学部, 教授 (20011091)

Co-Investigator(Kenkyū-buntansha) MITSUHASHI Shunsaku  Faculty of Engineering, University of Tokyo, 工学部, 助手 (20010845)
HISADA Toshiaki  Faculty of Engineering, University of Tokyo (BABA,Hiroshi), 工学部, 助教授 (40126149)
Project Period (FY) 1986 – 1987
Project Status Completed (Fiscal Year 1987)
Budget Amount *help
¥6,900,000 (Direct Cost: ¥6,900,000)
Fiscal Year 1987: ¥2,900,000 (Direct Cost: ¥2,900,000)
Fiscal Year 1986: ¥4,000,000 (Direct Cost: ¥4,000,000)
KeywordsCreep-Fatigue Interaction / Environmental Effect / Overstress / Internal Stress / Back Stress / Drag Stress / Life Prediction Equation / Time-Dependent Damage / 時間非依存損傷 / クリープ / 疲労 / 相互作用 / 304鋼 / 21 / 4Cr-1Mo鋼
Research Abstract

Creep-Fatigue Tests were made with 304 stainless steel at 650゜C and with 2 1/4Cr-lMo steel at 550゜C in arr and vacuum of 0.1 mPa and 0.1 <mu>Pa under a wide variety of strain loading conditions. Test data of stress-strain response and fatigue properties were stored in a data base for further analyses.
It was shown that the stress-strain response is independent of test environments for both steels. A measured stress is composed of the overstress and the internal stress. The internal stress of 304 steel is composed of the back stress. However, in 2 1/4Cr-1Mo steel, the internal stress is composed of the drag component and back component of the stress.
The overstress and back stress of 304 steel depend upon both inelastic strain rate and strain range. However, in 2 1/4Cr-1Mo steel, the overstress is independent of these test variables. The drag stress of this steel depends upon only a strain range. The back stress depends upon the inelastic strain rate. It was shown with both steels that the back stress depends upon the cyclic strain hardening or softening behavior.
The time-independent damage factor of both steels can be described with the overstress and a mean stress. Regarding the time-dependent damage factor, that of 304 steel can be described with the overstress. But that of 2 1/4Cr-1Mo steel can be described with the internal stress. Based on these results, an evaluation equation was derived for the pure creep-fatigue behavior of these two steels.
Based on the above equation, the environmental effect was seperated from the creep-fatigue interaction and was abalyzed with mechanical quantities of stress and strain. It was shown that the environmental effect is mainly affected by a strain rate. An evaluation oquation was obtained with respect ot the environmental damage described with mechanical parameters.

Report

(2 results)
  • 1987 Final Research Report Summary
  • 1986 Annual Research Report
  • Research Products

    (13 results)

All Other

All Publications (13 results)

  • [Publications] 浅山, 程, 橘, 朝田: 日本機械学会論文集A篇. 496. 2332-2237 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] 浅山, 程, 橘, 朝田: 日本機械学会論文集A篇. 497. (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama, T.;Cheng. S.;Asada, Y.;Mitsuhashi, S.;Tachibana, Y.: Proceedings of SMiRT-9. L. 227-237 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama, T.;Cheng, S. Z.;Tachibana, Y.;Ishikawa, A.;Asada, Y.: Proceedings of ICLCF-2. 265-270 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asada, Y.;Asayama, T.;Morishita, M.;Taguchi, K.: ASME PVP "Advances in Piping Analysis and Life Assessment". 129. 93-99 (1987)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama, T.;Cheng, S. Z.;Tachibana, Y;Asada, Y.: Bull-JSME.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama,T., Cheng,S.Z., Tachebana,Y. and Asada,Y.: "Creep-Fatigue Interaction of 2 1/4Cr-1Mo Steel im avery High Vacuum Environment" Transaction of JSME -A. 496. 2232-2237 (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama,T., Cheng,S.Z., Tachibana,Y. and Asada,Y.: "Analysis of Stress-Strain Response of 2 1/4Cr-1Mo Steel under Creep-Fatigue Loading" Transaction of JSME -A. 497. (1988)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama,T. Cheng,S.Z., Asada,Y., Mitsuhashi,S. and Taxhibana,Y.: "Creep-Fatigue Behavior of 2 1/4Cr-1Mo Steel at 550゜C in Air and Vacuum" Proceedings of SMiRT-9. 1. 227-237 (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asayama,T., Cheng,S.Z., Tachibana,Y., Ishikawa,A. and Asada,Y.: "Creep-Fatigue Behavior of 2 1/4Cr-1Mo Steel in Air and Vacuum" Proceedings of ICLCF-2. 265-270 (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asada,Y., Asayama,T., Morishita,M. and Taguchi,K.: "Creep-Fatigue Behavior of 304 Stainless Steel and 2 1/4Cr-1Mo Steel Based on the Overstress Concept" ASME-PVP "Advances in Piping Analysis and Life Assessment". 129. 93-99 (1987)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1987 Final Research Report Summary
  • [Publications] Asada,Y.: Proceedings of 2nd International Conference on Low-Cycle Fatigue and Elasto-Plastic Behavior of Materials(to be pubIished). (1987)

    • Related Report
      1986 Annual Research Report
  • [Publications] Asada,Y.: Proceedings of 9th Structural Mechanics in Reactor Technology. L. NO.L-6/1* (1987)

    • Related Report
      1986 Annual Research Report

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Published: 1987-03-31   Modified: 2016-04-21  

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