비파괴검사학회지 (Journal of the Korean Society for Nondestructive Testing)

  • 제33권2호
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  • Pages.147-153
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  • 2013
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  • 1225-7842(pISSN)
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  • 2287-402X(eISSN)
한국비파괴검사학회 (The Korean Society for Nondestructive Testing)
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원전 가압기 노즐 및 안전단 재료에 대한 기계적 물성시험 연구

A Study for Experiment to Measure Mechanical Properties of Pressurizer Nozzle and Safety-Ends in Nuclear Power Plant

  • 이경수 (한수원(주) 중앙연구원 기계재료연구소) ;
  • 이성호 (한수원(주) 중앙연구원 기계재료연구소) ;
  • 김진원 (조선대학교 공과대학 원자력공학과)
  • 투고 : 2013.03.18
  • 심사 : 2013.04.09
  • 발행 : 2013.04.30
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⟨ 이전 논문 다음 논문 ⟩

초록

최근 가압경수로형 원전의 가압기 노즐과 안전단 사이의 이종용접부에서 일차수응력부식균열에 대한 건전성 확보가 중요한 관심사항으로 대두되고 있다. 가압기 노즐은 SA508 Gr.3 저합금강이며 안전단은 F316L 스테인리스강으로, 이들 두 재료 사이에 용접재로는 Alloy 82/182가 사용되었다. 재료 결함에 대한 건전성 평가를 위해서는 재료의 기계적 물성치, 특히 인장물성과 파괴물성이 확보되어야 한다. 그러나, 일반적인 재료 규격과 시험성적서에서는 상온의 인장물성이 제공되지만 고온의 인장물성과 파괴인성이 제공되지 않는다. 따라서, 본 논문에서는 상온과 원전 운전온도에서 SA508 Gr.3과 F316L 스테인리스강에 대한 인장시험과 J-R 파괴인성시험을 수행하고 그 결과를 수록하였다.

Recently the primary water stress corrosion cracking(PWSCC) has occurred in the dissimilar metal weld region between pressurizer nozzle and safe-end in nuclear power plants(NPPs). As material of the pressurizer nozzle, SA508 Gr. 3 low alloy steel was used. F316L stainless steel and Alloy 82/182 were used as safe-end and weld metal, respectively. Although mechanical properties are needed for evaluation of the structural integrity against flaw in the material, material specification and standard don't supply those properties. Therefore, the present study conducted tensile and fracture toughness tests on SA508 Gr.3 and F316L stainless steel at ambient temperature and operating temperature of NPPs and reported the tested results.

키워드

참고문헌

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