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1989 Fiscal Year Final Research Report Summary

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)
Project Period (FY) 1988 – 1989
KeywordsLight-water cooled reactor / High temperature and pressurized water / Small specimen / Small punch testing / Stress corrosion cracking / Slow strain testing / Critical cracking potential
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.

  • Research Products

    (13 results)

All Other

All Publications (13 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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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
  • [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

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Published: 1993-03-26  

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