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Irradiation Assisted Stress Corrosion Cracking of Reactor Internals of Light Water Reactors

Research Project

Project/Area Number 02044012
Research Category

Grant-in-Aid for international Scientific Research

Allocation TypeSingle-year Grants
SectionJoint Research
Research InstitutionTohoku University

Principal Investigator

SHOJI Tetsuo  Research Institute for Fracture Technology, Faculty of Engineering, 工学部, 教授 (80091700)

Co-Investigator(Kenkyū-buntansha) WATANABE Yutaka  JSPS Post-Doctoral Fellow, 工学部, 学振特別研究員
SAKA Masumi  Faculty of Engineering, Tohoku University, 工学部, 助教授 (20158918)
HWANG I. S.  Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 原子力工学科, 助手
KOHSE G. E.  MIT Reactor Research Lab., Massachusetts Institute of Technology, 原子炉実験所, 助手
HARLING O. K.  MIT Reactor Research Lab., Massachusetts Institute of Technology, 原子炉実験所, 教授
BALLINGER R. G.  Dept. of Nuclear Engineering and Dept. of Materials Science and Engineering, Mas, 原子力及び材料科学科, 助教授
STEWART J.  東北大学, 工学部, 学振外国人特別研究員
Project Period (FY) 1990 – 1991
Project Status Completed (Fiscal Year 1991)
Budget Amount *help
¥5,100,000 (Direct Cost: ¥5,100,000)
Fiscal Year 1991: ¥2,500,000 (Direct Cost: ¥2,500,000)
Fiscal Year 1990: ¥2,600,000 (Direct Cost: ¥2,600,000)
KeywordsIrradiation Assisted Stress Corrosion Cracking / High Temperature Water / Grain Boundary Segregation / Cr-depletion / SSRT / Nondestructive Evaluation / Electro-chemical method / IGSCC / 照射誘起偏析 / 低ひずみ速度 / 不純物 / 中性子照射 / γ線照射
Research Abstract

The objective of this research is to develop a nondestructive evaluation method for detection of radiation induced segregation such as Cr-depletion with very narrow width and impurities segregation. These changes in grain boundary chemistries are possible causes of Irradiation Assisted Stress Corrosion Cracking. Several heats of Type 304 Stainless Steels including high purity, commercial purity, nuclear grade, low sulfur materials. In addition to grain boundary chemical analysis, slow strain rate tests were performed in oxygenated high temperature water at 288゚C. Results can be summarized as follows,
1. Modified EPR can detect irradiation induced narrow Cr depletion.
2. RIS was strongly affected by carbon content and nuclear grade material showed the highest resistance to IGSCC.
3. Impurity segregation can be quantitatively evaluated by total charge density measured at-1050mv for one hours in 5N-H_2SO_4
4. These NDE technique can be applied to TEM disc specimens by RIS detector.
5. IGSCC region can be mapped in terms of Cr-depletion and impurity segregation.
6. Further research is needed to evaluate the segregation of B and N which can transmute to form He and H and results in grain boundary weakening.
Taking account of those grain boundary analysis and it relation to IGSCC, IASCC mechanisms can be made clear.

Report

(3 results)
  • 1991 Annual Research Report   Final Research Report Summary
  • 1990 Annual Research Report
  • Research Products

    (18 results)

All Other

All Publications (18 results)

  • [Publications] T.Shoji,K.Yamaki,R.G.Ballinger,I.S.Hwang: "Grain Boundary Segregation and Intergranular Stress Corrosion Cracking Susceptibility of Austenitic Stainless Steels in High Temperature Water" 5th International Symposium on Environmental Degradation of Materials in Nuclear Power System,Water Reactor,1992,August. (1992)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] 岩渕 義昌,庄子 哲雄,藤本: "照射誘起応力腐食割れ感受性評価のための基礎的研究" 腐食防食協会春期講演会. (1992)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] Tetsuo Shoji;Satoshi Mori;Hideya Anzai;Jiro Kuniya: "Quantitative Evaluation of Stress Corrosion Crack Grack Growth Behavior on Inconel 600 in a Simulated LWR Environment" Life Prediction of Corrodible Structure,Sept.23-26,1991,Cambridge,U.K.

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] 斎藤 喜久,庄子 哲雄,渡辺 豊: "電気化学的手法によるステンレス鋼の材質劣化現位置評価技術の開発" 日本機械学会論文集(A編). 57. 164-170 (1991)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] Y.Watanabe;T.Shoji: "The Evaluation of In-Service Materials Degradation of Low-Allow Steels by the Electrochemical Method" Metallurgical Transactions A. 22A. 2097 (1991)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] T. Shoji, K. Yamaki, R. G. Ballinger, I. S. Hwang: "Grain Boundary Segregation and Intergranular Stress Corrosion Cracking Susceptibility of Austenitic Stainless Steels in High Temperature Water" 5th International Symposium on Environmental Degradation of Materials in Nuclear Power System, Water Reactor, 1992, August. (1992)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] Y. Iwabuchi, T. Shoji, T. Fujimoto: "Research on Irradiation Assisted Stress Corrosion cracking" Proceedings of Spring Annual Meeting of Japan Society of Corrosion Engineers. (1992)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] T. Shoji, S. Mori, H. Anzai, J. Kuniya: "Quantitative Evaluation of Stress Corrosion Crack Growth Behavior on Inconel 600 in a Simulated LWR Environment Research of IASCC" Life Prediction of Corrodible Structure, Sept. 23-26, 1991, Cambridge, U. K.

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] Y. Saito, T. Shoji, Y. Watanabe: "In-Situ Electro-Chemical Measurement of Materials Degradation of Austenitic Stainless Steels" Trans JSME, series A. 57. 164-170 (1991)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] Y. Watanabe, T. Shoji: "The Evaluation of In-Service Materials Degradation of Low-Allow Steels by the Electrochemical Method" Metallurgical Transactions A. 22A. 2097 (1991)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1991 Final Research Report Summary
  • [Publications] T.Shoji,K.Yamaki,R.G.Ballinger,I.S.Hwang: "Grain Boundary Segregation and Intergranular Stress Corrosion Cracking Susceptibility of Austenitic Stainless Steels in Hign Temperature Water" 5th International Symposium on Environmental Degradation of Materials in Nuclear Power System,Water Reactor,1992,August. (1992)

    • Related Report
      1991 Annual Research Report
  • [Publications] 岩渕 義昌,庄子 哲雄,藤本: "照射誘起応力腐食割れ感受性評価のための基礎的研究" 腐食防食協会春期講演会. (1992)

    • Related Report
      1991 Annual Research Report
  • [Publications] Tetsuo Shoji Satoshi Mori Hideya Anzai,jiro Kuniya: "Quantitative Evaluation of Stress Corrosion Crack Growth Behavior on Inconel 600 in a Simulated LWR Environment" Life Prediction of Corrodible Structure,Sept.23-26,1991,Cambridge,U.K.

    • Related Report
      1991 Annual Research Report
  • [Publications] 斎藤 喜久,庄子 哲雄,渡辺 豊: "電気化学的手法によるステンレス鋼の材質劣化現位置評価技術の開発" 日本機械学会論文集(A編). 57. 164-170 (1991)

    • Related Report
      1991 Annual Research Report
  • [Publications] Y.Watanabe T.Shoji: "The Evaluation of In-Service Materials Degradation of Low-Allow Steels by the Electrochemical Method" Metallurgical Transactions A. 22A. 2097 (1991)

    • Related Report
      1991 Annual Research Report
  • [Publications] T.Shoji,K.Yamaki,R.G.Ballinger,I.S.Hwang: "Grain boundary Segregation and Intergranular Stress Corrosion Cracking Susceptibility of Austenitic Stainless Steels in High Temperature Water" 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems. (1991)

    • Related Report
      1990 Annual Research Report
  • [Publications] 庄子 哲雄、八巻 健一、林 慎一郎: "オ-ステナイト系ステンレス鋼SUS304の粒界応力腐食割れ感受性に及ぼす粒界偏析の影響" シンポジウム講演論文集“破壊と新技術" 日本機械学会. No.900ー50. (1990)

    • Related Report
      1990 Annual Research Report
  • [Publications] 庄子 哲雄、吉田 謙一、森 聡: "高温水中におけるNi基合金の応力腐食割れに関する研究" シンポジウム講演論文集“破壊と新技術" 日本機械学会. No.900ー50. (1990)

    • Related Report
      1990 Annual Research Report

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Published: 1990-04-01   Modified: 2016-04-21  

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