Corrosion Science and Technology

  • 제22권3호
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  • Pages.214-219
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  • 2023
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  • 1598-6462(pISSN)
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  • 2288-6524(eISSN)
한국부식방식학회 (The Corrosion Science Society of Korea)
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원자력발전소 증기발생기 Alloy 690 전열관 재료의 규칙화 반응

Ordering of Alloy 690 Steam Generator Tubings in a Nuclear Power Plant

  • 황성식 (한국원자력연구원, 재료안전기술개발부) ;
  • 최민재 (한국원자력연구원, 재료안전기술개발부) ;
  • 김성우 (한국원자력연구원, 재료안전기술개발부)
  • Seong Sik Hwang (Korea Atomic Energy Research Institute, Materials Safety Technology Development Division) ;
  • Min Jae Choi (Korea Atomic Energy Research Institute, Materials Safety Technology Development Division) ;
  • Sung Woo Kim (Korea Atomic Energy Research Institute, Materials Safety Technology Development Division)
  • 투고 : 2022.09.06
  • 심사 : 2023.04.04
  • 발행 : 2023.06.30
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초록

Considering the case in the United States where most nuclear power plants with an initial design life of 40 years continue to operate until 60 or 80 years after undergoing material soundness evaluation, it is time to plan a more robust long-term operation strategy for nuclear power plants in Korea. There are some reports that SRO/LRO might be formed when Alloy 690 is heat treated for 10,000 hours to 100,000 hours at 360 to 450 ℃. The possibility of LRO formation in Alloy 690 steam generator tubings of Kori nuclear power plant unit 1 (Kori-1) was investigated using existing research papers. The mechanism in which SRO/LRO occurred was also surveyed. Alloy 690 was found to be more likely to cause ordering than Alloy 600 in terms of alloy composition. The ordering could be evaluated through changes in material properties. However, it is difficult to evaluate it from a microstructural point of view. The likelihood of LRO in Alloy 690 of the Kori-1 plant operated at 320 ℃ for 19 years seemed to be low in terms of time and exposure temperature.

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과제정보

이 논문은 2021년도 과학기술정보통신부의 재원으로 한국연구재단의 지원(2021M2E4A1037979, 고리 1호기 1차계통 압력경계 재료 실증체계 구축)으로 수행되었다.

참고문헌

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