• Search Research Projects
  • Search Researchers
  • How to Use
  1. Back to previous page

RESEARCH ON IRRADIATION ASSISTED STRESS CORROSION CRACKING(IASCC) OF REACTOR INTERNALS

Research Project

Project/Area Number 01044014
Research Category

Grant-in-Aid for international Scientific Research

Allocation TypeSingle-year Grants
SectionJoint Research
Research InstitutionTOHOKU UNIVERSITY

Principal Investigator

SHOJI Tetsuo  TOHOKU UNIV. FACULTY OF ENGNG, RES. INST. FRACTURE TECHNOLOGY, PROFESSOR, 工学部, 教授 (80091700)

Co-Investigator(Kenkyū-buntansha) G.E Kohse  マサチューセッツ工科大学, 原子炉実験所, 助手
O.K Harling  マサチューセッツ工科大学, 原子炉実験所, 教授
M.J Driscoll  マサチューセッツ工科大学, 原子力工学科, 教授
R.G Ballinge  マサチューセッツ工科大学, 材料科学科, 助教授
TAKAHASHI Hideaki  TOHOKU UNIV. FACULTY OF ENGNG, RES. INST. FRACTURE TECHNOLOGY, PROFESSOR, 工学部, 教授 (10005267)
DRISCOLL M.J.  M.I.T. DEPT. NUCLEAR ENGNG. PROFESSOR
HARLING O.K.  M.I.T. NUCLEAR REACTOR LAB., PROFESSOR
BALLINGER R.G.  M.I.T. DEPT. MATERIALS SCIENCE AND ENGNG., ASSOCIATE PROFESSOR
KOHSE G.e.  M.I.T. NUCLEAR REACTOR LAB., RESEARCH ASSOCIATE
Project Period (FY) 1989
Project Status Completed (Fiscal Year 1989)
Budget Amount *help
¥3,500,000 (Direct Cost: ¥3,500,000)
Fiscal Year 1989: ¥3,500,000 (Direct Cost: ¥3,500,000)
KeywordsIRRADIATION ASSISTED STRESS CORROSION CRACKING / SENSITIZATION / GRAIN BOUNDARY SEGREGATION / Cr DEPLATION SLOW STRAIN RATE TESTS / SULFUR / PHOSPHOROUS / INTERGRANULAR CRACKING EPR / CORIOU TEST / EPR / Coriou試験
Research Abstract

OBJECTIVES OF THIS RESEARCH ARE TO SIMULATE THE GRAIN BOUNDARY STRUCTURE AND CHEMISTRY OF IRRADIATION ASSISTED GRAIN BOUNDARY SEGREGATION BY THERMAL TREATMENTS ANF TO CHARACTERIZE THE GRAIN BOUNDARIES IN CORRELATION WITH IGSCC SUSCEPTIBILITY BY MEANS OF SSRT IN SIMULATED LWR WATER ENVIRONMENTS.
IN THIS YEAR, MAIN EFFORTS HAVE BEEN PAID FOR DETERMINATION OF MATERIALS SELECTION FOR THE PURPOSE MENTIONED ABOVE AND FINALIZED 7 AUSTENITIC STAINLESS STEELS WITH A VARIATION OF IMPURITY CONTENTS.
CHARACTERIZATION OF GRAIN BOUNDARY WERE PERFORMED BY EPR AND CORIOU TESTS. IGSCC WAS REPRODUCED ON THE MATERIALS WITH GRAIN BOUNDARY SEGREGATION OF SULFUR AND PHOSPHOROUS AND WITH NON SENSITIZED CONDITIONS. HIGH CRACKING SUSCEPTIBILITY WAS OBTAINED ON THE SPECIMENS WITH SEGRAGATION.

Report

(1 results)
  • 1989 Final Research Report Summary
  • Research Products

    (6 results)

All Other

All Publications (6 results)

  • [Publications] TETSUO SHOJI,KIYOSHI KIUCHI AND TATSUO KONDO: "MATERIALS COMPATIBILITY WITH HIGH TEMPERATURE WATERS AND LONG TERM STABILITY IN NUCLEAR REACTOR ENVIRONMENTS" PROC.OF FOURTH INTERNATION SYMPOSIUM ON ENVIRONMENTAL DEGRADATION MATERIALS IN NUCLEAR POWER SYSTEMS-LIGHT WATER REACTORS(INVITED). (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] TETSUO SHOJI,SHIN-ICHI MORIYA AND MAKOTO TADA: "COMPUTER SIMULATION OF ENVIRONMENTALLY ASSISTED CRACKING OF RPV STEELS IN LWR ENVIRONMENTS" PROC.OF FOURTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-LIGHT WATER REACTORS. (1990)

    • 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,八巻健一: "非鋭敏化オ-ステナイト系ステンレス鋼の高温水中粒界応力腐食割れに及ぼす不純物の影響" 「破壊と新技術」シンポジウム,日本機械学会. 8月. (1990)

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] TETSUO SHOJI, KIYOSHI KIUCHI AND TATSUO KONDO: "MATERIALS COMPATIBILITY WITH HIGH TEMPERATURE WATERS AND LONG TERM STABILITY IN NUCLEAR REACTOR ENVIRONMENTS(INVITED)" PROC. OF FOURTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-LIGHT WATER REACTORS. (1990)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] TETSUO SHOJI, SHINICHI MORIYA AND MAKOTO TADA: "COMPUTER SIMULATION OF ENVIRONMENTALLY ASSISTED CRACKING OF RPV STEELS IN LWR ENVIRONMENTS" PROC. FOURTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-LIGHT WATER REACTORS. (1990)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary
  • [Publications] TETSUO SHOJI AND KENICHI YAMAKI: "EFFECTS OF IMPURITIES UPON IGSCC OF NON-SENSITIZED AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER" PROC. JSME SYMPOSIUM ON STRENGTH EVALUATION OF ADVANCED MATERIALS. AUGUST. (1990)

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      1989 Final Research Report Summary

URL: 

Published: 1989-04-01   Modified: 2016-04-21  

Information User Guide FAQ News Terms of Use Attribution of KAKENHI

Powered by NII kakenhi