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Development of Miniaturized Specimen Technique for Evaluating Stress Corrosion Cracking Suspeptibility

Research Project

Project/Area Number 63302023
Research Category

Grant-in-Aid for Co-operative Research (A)

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

Principal Investigator

TAKAHASHI Hideaki  Tohoku Univ., RIFT, Professor, 工学部, 教授 (10005267)

Co-Investigator(Kenkyū-buntansha) NAKAJIMA Hajime  JAERI, 室長
MISAWA Toshihei  Muroran Inst. Tech., Dept. Metall. Engng., Associate Professor, 工学部, 助教授 (70005982)
TAMAKAWA Kinji  Tohoku Univ., RIFT, Research Associate, 工学部, 助手 (30005368)
HASHIDA Toshiyuki  Tohoku Univ., RIFT, Lecturer, 工学部, 助手 (40180814)
SHOJI Tetsuo  Tohoku Univ., RIFT, Professor, 工学部, 教授 (80091700)
三沢 俊平  室蘭工業大学, 工学部, 助教授 (90104041)
Project Period (FY) 1988 – 1989
Project Status Completed (Fiscal Year 1989)
Budget Amount *help
¥10,700,000 (Direct Cost: ¥10,700,000)
Fiscal Year 1989: ¥4,900,000 (Direct Cost: ¥4,900,000)
Fiscal Year 1988: ¥5,800,000 (Direct Cost: ¥5,800,000)
KeywordsLight-water cooled reactor / High temperature and pressurized water / Small specimen / Small punch testing / Stress corrosion cracking / Slow strain testing / Critical cracking potential / 高温高圧水還境 / 軽小炉 / 水冷却型核融合炉 / A508鋼オーステナイト系ステンレス鋼 / 応力腐食割れ試験 / 低ひずみ速度引張り試験 / 硫黄含有量 / ひずみ速度
Research Abstract

The small specimen test technique (SSTT) combined with electrochemical measurements for irradiated miniaturized specimens has been developed to evaluate the resistance to stress corrosion cracking (SCC) and corrosion of fusion reactor structural steels in water-coolant environment under irradiation. Two newly developed apparatus for a small punch (SP) testing and a slow-strain-rate test (SSRT) using miniaturized specimens in high temperature and high pressure aqueous solutions under applied potential conditions were successfully demonstrated for Type 304 austenitic and HT-9 ferritic stainless steels. Anodic polarization curves were measured and SP fracture energies of stress corrosion were obtained as a function of potential and strain rate. SP-SCC tests using small specimens showed that sensitized Type 304 steel had the susceptibility zones to SCC at the regions of corrosion potential and transpassive potential, whereas the solution-annealed Type 304 and HT-9 steels had the potential independence of SP energies without lowering by the stress corrosion. Surface films were examined by scanning electron microscope, Auger electron spectroscopy and laser Raman spectroscopy. There was the relationship between nature of surface films and SCC susceptibility. The strain rates smaller than 1.5x10^<-6> s^<-1> were necessary for a significant reduction of the elongation required for intergranular stress corrosion of sensitized Type 304 steel in the SSRT using miniaturized tensile specimens. The strain rate value that brought about the highest SCC susceptibility in sensitized Type 304 steel was larger than that of the popular SSRT using the uniaxial tensile specimens because of the stronger bulge deformation in SP tests. The SP-SCC test may therefore develop as a rapid and useful stress-corrosion testing method using small specimens in order to evaluate the SCC resistance of irradiated materials in high temperature water environments.

Report

(3 results)
  • 1989 Annual Research Report   Final Research Report Summary
  • 1988 Annual Research Report
  • Research Products

    (22 results)

All Other

All Publications (22 results)

  • [Publications] 庄子哲雄、相沢周二、高橋秀明: "軽水炉水環境下における原子炉圧力容器鋼の応力腐食割れ" 日本機械学会論文集(A編). 54. 1251-1257 (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Shoji,H.Takahashi,S.Aizawa and M.Saito: "Effect of Sulfate Contamination,Sulfurin Steels and Strain Rate on Critical Cracking Potential for SCC" Proc.3rd Int'l Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor,EDs.,G.J.Theusand J.R.Weeks,The Metallungical Society. 251-259 (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] 庄子哲雄、高橋秀明、多田真也: "低合金鋼の高温高圧水中応力腐食割れ挙動のコンピュ-タ・シミュレ-ション" 第35回腐食防食討論会講演集. 409-412 (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] 庄子哲雄、斉藤幹男: "圧力容器鋼の高温高圧水中応力腐食割れ臨界電位に及ぼす材料環境及び力学因子の影響" 第35回腐食防食討論会講演集. 425-428 (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Misawa,Y.Hamaguchi,M.Saito: "Stress Corrosion Cracking and Hydrogen Embrittlement Studies of Austenitic and Ferritic Steels by Small Punch Test" J.Nuclear Materials. 155-157. 749-753 (1988)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Misawa,S.Nagata,N.Aoki,J.Ishizaka,Y.Hamaguchi: "Fracture Toughness Evaluation of Fusion Reactor Structural Steels at Low Temperatures by Small Punch Tests" J.Nuclear Materials. 169. 225-232 (1989)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Misawa,T.Ohtsuka,M.Seo,M.Saito: "Comparision of Stress Corrosion Cracking Susceptibility of Austenitic and Ferritic Stainless Steels in Small Punch Testing" J.Nuclear Materials(in press). (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Misawa,K.Suzuki,M.Saito,Y.Hamaguchi: "Determination of a Minimum Quantity of Irradiated Ferritic Steel Specimens for Small Punch DBTT Testing" J.Nuclear Materials(in press). (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] M.Suzuki,M.Eto,T.Misawa et al.: "Evaluation of Toughness Degradiation by Small Punch(SP)Tests for Neutron Irradiated 2 1/4 Cr-1Mo Steel" (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Shoji,K.Kiuchi and T.Kondo: "Materials Compatibility with High Temerature Waters and Long Term Stability in Nuclear Reactor Envipronments" Proc.Fourth International Symposium on Environmental Degradation of Materials in Unclear Power Systems-Water Reactors(to be published). (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T. Shoji, H. Takahashi, S. Aizawa, and M. Saito: "Effect of Sulfate Contamination Sulfur in Steels and Strain Rate on Critical Cracking Potential for SCC" Proc. 3rd Int. Sympo. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor. 251-259 (1988)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T. Misawa, Y. Hamaguchi, M. Saito: "Stress Corrosion Cracking and Hydrogen Embrittlement Studies of Austenitic and Ferritic Steels by Small Punch Test." J. Nuclear Materials. 155-157. 749-753 (1988)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T. Misawa, S. Nagata, N. Aoki, J. Ishizaka, and Y. Hamaguchi: "Fracture Toughness Evaluation of Fusion Reactor Structural Steels at Low Temperatures by Small Punch Tests." J. Nuclear Materials. 169. 225-232 (1989)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] T.Misawa,S.Nagata,N.Aoki,J.Ishizaka,Y.Hamaguchi: "Fracture Toughness Evaluation of Fusion Reactor Structural Steels at Low Temperatures by Small Punch Tests" J.Nuclear Materials. 225-232 (1989)

    • Related Report
      1989 Annual Research Report
  • [Publications] T.Misawa,T.Ohtsuka,M.Seo,M.Saito: "Comparision of Stress Corrosion Cracking Susceptibility of Austenitic and Ferritic Stainless Steels in Small Punch Testing" J.Nuclear Materials. (1990)

    • Related Report
      1989 Annual Research Report
  • [Publications] T.Misawa,K.Suzuki.M.Saito,Y.Hamaguchi: "Determination of a Minimum Quantity of Irradiated Ferritic Steel Specimens for Small Punch DBT testing" J.Nuclear Materials. (1990)

    • Related Report
      1989 Annual Research Report
  • [Publications] T.Suzuki,M.Eto,T.Misawa et al.: "Evaluation of Toughness Degradiation by Small Punch(SP)Tests for Neutron Irradiated 21/4 Cr-1Mo Steel" J.Nuclear Materials. (1990)

    • Related Report
      1989 Annual Research Report
  • [Publications] T.Shoji,K.Kiuchi and T.Kondo: "Materials Compatibility with High Temperature Waters and Long Term Stablity in Nuclear Reactor Environments" Proc Fourth International Symposium on Environmental Degradation of Materials in Unclear Power Systems-Water Reactors. (1990)

    • Related Report
      1989 Annual Research Report
  • [Publications] 庄子哲雄、相沢周二、高橋秀明: 日本機械学会論文集(A編). 54. 1251-1257 (1988)

    • Related Report
      1988 Annual Research Report
  • [Publications] T.Shoji,;H.Takahashi,;S.Aizawa,;M.Saito.: Proc.3rd.Int'l Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor,Eds,G.J.Theus and J.R.Weeks,The Metallurgical Society. 251-259 (1988)

    • Related Report
      1988 Annual Research Report
  • [Publications] 庄子哲雄、高橋秀明、多田真也: 第35回腐食防食討論会講演集. 409-412 (1988)

    • Related Report
      1988 Annual Research Report
  • [Publications] 庄子哲雄、斉藤幹男: 第35回腐食防食討論会講演集. 425-428 (1988)

    • Related Report
      1988 Annual Research Report

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Published: 1988-04-01   Modified: 2016-04-21  

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