Corrosion Science and Technology

The Corrosion Science Society of Korea (한국부식방식학회)
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Effects of Proton Irradiation on the Microstructure and Surface Oxidation Characteristics of Type 316 Stainless Steel

양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향

  • Lim, Yun-Soo (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dong-Jin (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Hwang, Seong Sik (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Choi, Min Jae (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Cho, Sung Whan (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute)
  • 임연수 (한국원자력연구원 재료안전기술개발부) ;
  • 김동진 (한국원자력연구원 재료안전기술개발부) ;
  • 황성식 (한국원자력연구원 재료안전기술개발부) ;
  • 최민재 (한국원자력연구원 재료안전기술개발부) ;
  • 조성환 (한국원자력연구원 재료안전기술개발부)
  • Received : 2021.05.25
  • Accepted : 2021.06.14
  • Published : 2021.06.30
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Abstract

Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 ℃, the various defects induced by this proton irradiation were characterized with microscopic equipment. In our observations irradiation defects such as dislocations and micro-voids were clearly revealed. The typical irradiation defects observed differed according to depth, indicating the evolution of irradiation defects follows the characteristics of radiation damage profiles that depend on depth. Surface oxidation tests were conducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understand the role irradiation defects play in surface oxidation behavior and also to investigate the resultant irradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primary water. We found that Cr and Fe became depleted while Ni was enriched at the grain boundary beneath the surface oxidation layer both in the non-irradiated and proton-irradiated specimens. However, the degree of Cr/Fe depletion and Ni enrichment was much higher in the proton-irradiated sample than in the non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructural and microchemical changes induced by proton irradiation all appear to significantly increase the susceptibility of austenitic 316 stainless steel to IASCC.

Keywords

Acknowledgement

이 논문은 2017년도 과학기술정보통신부의 재원으로 한국과학기술재단의 지원(2017M2A8A4015155, 고내식구조재료 부식균열 개시평가 및 대응기술 개발)과 2019년도 산업통상자원부의 재원으로 한국에너지기술평가원의 지원(20191510301140, 해체원전 원자로 내부구조물 베플포머볼트 조사유기 응력부식 균열 열화 특성 분석 기술개발)을 받아 수행된 연구입니다.

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