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FRACTURE MECHANICS APPROACH OF ENVIRONMENTALLY ASSISTED CRACKING BY MEANS OF SLOW STRAIN RATE TEST

Research Project

Project/Area Number 60550045
Research Category

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

Allocation TypeSingle-year Grants
Research Field 機械材料工学
Research InstitutionTOHOKU UNIVERSITY

Principal Investigator

SHOJI TETSUO  FACULTY OF ENGINEERING, TOHOKU UNIV., ASSOCIATE PRFESSOR, 工学部, 助教授 (80091700)

Co-Investigator(Kenkyū-buntansha) TAMAKAWA KINJI  FACULTY OF ENGINEERING, TOHOKU UNIV., RESEARCH ASSOCIATE, 工学部, 助手 (30005368)
Project Period (FY) 1985 – 1986
Project Status Completed (Fiscal Year 1986)
Budget Amount *help
¥1,800,000 (Direct Cost: ¥1,800,000)
Fiscal Year 1986: ¥700,000 (Direct Cost: ¥700,000)
Fiscal Year 1985: ¥1,100,000 (Direct Cost: ¥1,100,000)
KeywordsFinite Element Method / Time domain Analysis / Crack Tip Strain Rate / LWR Pressure Vessel / Pressurized High Temperature Water / Slow Strain Rate Test / 臨界電位 / 破壊力学
Research Abstract

BY APPLYING FRACTURE MECHANICS APPROACH TO SSRT AS A ASSESSMENT TECHNIQUE OF STRESS CORROSION CRACKING SUSCEPTIBILITY, IT BECAME POSSIBLE TO USE SSRT AS A QUANTITATIVE EVALUATION TECHNIQUE FOR STRUCTURAL INTEGRITY ASSESSMENT RATHER THAN QUALITATIVE ONE SUCH AS GO-NO GO SCREENING TESTS. MAIN CONCLUSIONS CAN BE SUMMARIZED AS FOLLOWS,
1. TIME BASE CRACK GROWTH RATE WAS FOUND AS A SUITABLE PARAMETER REPRESENTING CRACK TIP STRAIN RATE BY FEM ANALYSIS AND THIS FINDING GAVE A PHYSICAL BASIS TO THE TIME DOMAIN ANALYSIS.
2. SSRT TESTS WERE PERFORMED ON NUCLEAR REACTOR PRESSURE VESSEL STEELS, SA508 CLASS III AND SA533B CLASS I IN HIGH TEMPERATURE WATER BY USE OF PLAIN AND PRE-CRACKED SPECIMENS. CRACK INITIATION AND PROPAGATION BEHAVIOR WERE EVALUATED IN TERMS OF FRACTURE MECHANICS PARAMETERS AND, SPECIALLY, THRESHOLD BEHAVIOR AND CRACK GROWTH RATE WERE QUANTITATIVELY EVALUATED. THIS CRACK GROWTH RATE OBTAINED FROM SSRT WAS CAMPARED WITH THOSE OBTAINED BY CONSTANT LOAD SCC TESTS.
3. EFFECTS OF SULPHATE CONTAMINATION AND SULPHUR CONTENT IN STEEL ON CRACK GROWTH RATE, THRESHOLD BEHAVIOR AND SCC CRITICAL POTENTIAL WERE EXAMINED AND THE SIGNIFICANCE OF THESE EFFECTS IN STRACTURAL INTEGRITY ASSESSMENT WAS EMPHASIZED.
4. A NEW FLAW EVALUATION PROCEDURE TAKING INTO CONSIDERATION SUBCRITICAL CRACK GROWTH BASED UPON TIME DOMAIN ANALYSIS WAS PROPOSED AND NOW BEING REVIEWED BY INTERNATIONAL CYCLIC CRACK GROWTH RATE GROUP.

Report

(1 results)
  • 1986 Final Research Report Summary
  • Research Products

    (19 results)

All Other

All Publications (19 results)

  • [Publications] 相沢周二: 日本機械学会講演論文集. 860. 285-290 (1986)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 庄子哲雄: 第33回腐食防食討論会予稿集 腐食防食協会. 39-42 (1986)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: PROCEEDINGS OF THE SECOND IAEA SPECIALISTS' MEETING ON SUBCRITICAL CRACK GROWTH,NUREG/CP-0067,MEA-2090,ED.W.H.CALLEN. 2. 99-117 (1986)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: 9TH INTERNATIONAL CONFERENCE ON STRUTURAL MECHANICS IN REACTOR TECHNOLOGY(SMIRT),LAUSANNE,SWITZERLAND,AUGUST,1987.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] HIDEAKI TAKAHASHI: 9TH INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY(SMIRT),LAUSANNE,SWITZERLAND,AUGUST,1987.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] JOHN CONGLETON: 9TH INTENATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY(SMIRT),LAUSANNE,SWITZERLAND,AUGUST,1987.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: TRANS.ASME,JOURNAL OF PRESSURE VESSEL TECHNOLOGY,SUBMITTED FOR PUBLICATION.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] 庄子哲雄: 日本機械学会論文集.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: 3RD INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS--WATER REACTOR,TMS,ANS AND NACE,TRAVERSE CITY,MICHIGAN,USA,AUGUST,1987.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "STRUCTRAL INTEGRITY ASSESSMENT OF RPV AND SUBCRITICAL CRACK GROWTH" TRANS JSME (IN JAPANESE). 89. 37-43 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] SHU-JI AIZAWA: "STRESS CORROSION CRACK OF RPV STEELS IN LWR WATER ENVIRONMENTS" PROCEEDING OF JSME, NODA (IN JAPANESE). 860. 285-290 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "ON THE CRITICAL CRACKING POTENTIALS FOR SCC OF RPV STEELS IN PRESSURIZED HIGH TEMPERATURE WATER" PROCEEDING OF 33RD MEETING OF JAPAN CORROSION ENGINEERING SOCIETY, AUG., 1986 OKINAWA (IN JAPANESE). 39-42 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "MECHANISTIC UNDERSTANDING OF ENVIRONMENTALLY ASSISTED CRACKING OF RPV STEELS IN LWR PRIMARY COOLANTS" PROCEEDINGS OF THE SECOND IAEA SPECIALISTS' MEETING ON SUBCRITICAL CRACK GROWTH, NUREG/CP-0067, MEA-2090, ED. W. H. CULLEN. 2. 99-117 (1986)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "CRITICAL CRACKING POTENTIAL FOR STRESS CORROSION CRACKING OF NUCLEAR PRESSURE VESSEL STEELS IN PRESSURIZED HIGH TEMPERATURE WATERS" 9TH INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY (SMIRT), LANSANNE, SWITZERLAND, AUGUST, 1987.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] HIDEAKI TAKAHASHI: "TIME DOMAIN ANALYSIS FOR QUANTITATIVE EVALUATION OF EAC AND ITS RELEVANCE TO LIFE EVALUATION PROCEDURE OF RPV" 9TH INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY (SMIRT), LAUSANNE, SWITZERLAND, AUGUST, 1987.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] JOHN CONGLETON: "SLOW STRAIN RATE TESTING OF RPV STEELS IN HIGH TEMPERATURE WATER" 9TH INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY (SMIRT), LAUSANNE, SWITZERLAND, AUGUST, 1987.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "QUANTITATIVE PREDICTION OF ENVIRONMENTALLY ASSISTED CRACKING BASED ON CRACK TIP STRAIN RATE" TRANS. ASME, JOURNAL OF PRESSURE VESSEL TECHNOLOGY, SUBMITTED FOR PUBLICATION.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "COMPUTOR SIMULATION OF ENVIRONMENTALLY ASSISTED CRACKING OF NUCLEAR PRESSURE VESSEL STEELS IN LWR ENVIRONMENT" JSME SENDAI MEETING, OCT., 1987, NATORI.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary
  • [Publications] TETSUO SHOJI: "EFFECTS OF SULPHATE CONTAMINATION, SULFUR CONTENT IN STEEL AND STRAIN RATE ON CRITICAL CRACKING POTENTIAL FOR SCC OF PROSSURE VESSEL STEELS IN PRESSURIZED HIGH TEMPERATURE WATERS" 3RD INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS--WATER REACTOR, TMS, ANS AND NACE, TRAVERSE CITY, MICHIGAN, USA, AUGUST, 1987.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1986 Final Research Report Summary

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

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