Journal of Ocean Engineering and Technology (한국해양공학회지)

Korean Society of Ocean Engineers (한국해양공학회)
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The Evaluation for Elastic-Plastic Fracture Toughness in a Reactor Pressure Vessel Steel(SA508-3)

원자력 압력용기강(SA508-3)의 탄소성 파괴인성 평가

  • 오세욱 (동아대학교, 공과대학기계공학과) ;
  • 윤한기 (동아대학교, 공과대학기계설계과) ;
  • 임만배 (동아대학교, 공과대학기계공학과)
  • Published : 1993.12.01
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Abstract

The elastic-plastic fracture thoughness J sub(IC) of Nuclear Reactor Vessel Steel(SA 508-3) which has high toughness was discussed at temperatures RT, $-20^{\circ}C$, $200^{\circ}C$ and 1/2/CT specimen was used for this study. Especially the two methods recommended in ASTM and JSME were compared. It was difficult to find J sub(IC) by ASTM R-curve method with the specimen used for this research, while JSME R-curve method yielded good result. The stretched zone width menthod gave slightly larger J sub(IC) values than those by the R-curve method for SA 508-3 steel.

Keywords

References

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