DOI QR코드

DOI QR Code

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

원자력발전소 증기발생기 Alloy 690 전열관 재료의 규칙화 반응

  • 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)
  • 황성식 (한국원자력연구원, 재료안전기술개발부) ;
  • 최민재 (한국원자력연구원, 재료안전기술개발부) ;
  • 김성우 (한국원자력연구원, 재료안전기술개발부)
  • Received : 2022.09.06
  • Accepted : 2023.04.04
  • Published : 2023.06.30

Abstract

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.

Keywords

Acknowledgement

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

References

  1. Ursula von der Leyen, https://www.dw.com/en/european-commission-declares-nuclear-and-gas-to-be-green/a-60614990, Europen Commission, https://ec.europa.eu/commission/presscorner/detail/en/mex_22_6484 (2022).
  2. E. Pierson, and J. Stubbe, Possible Effects of Short and Long Range Order on the In-Service Behaviour of Nickel Alloys Used for Steam Generator Tubes, LABORELEC, pp. 1 - 23 (1989).
  3. G. A.Young, and D. R. Eno, Long Range Order in Model Ni-Cr-X Alloys, Proc. Fontevraud 8-Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance, and Reliability, SFEN, Avignon, France (2014).
  4. P. Chou, Alloy 690 Long-Range Ordering (LRO), EPRI Alloy 690/52/152 Primary Water Stress Corrosion Cracking Research Collaboration Meeting, Santa Barbara,USA, December 2 (2021).
  5. Anil Virkar, https://my.eng.utah.edu/~lzang/images/lecture-25.pdf.
  6. R. Mouginot, pH.D, DOCTORAL DISSERTATIONS 81, Aalto University publication series (2017).
  7. G. A. Young, J. D. Tucker, and D. R. Eno. The Kinetics of Long Range Ordering in Ni-Cr and Ni-Cr-Fe Alloys, Proc. 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. NACE, Asheville, NC, USA (2013).
  8. A. Marucco, Atomic ordering and α'-Cr phase precipitation in long-term aged Ni3Cr and Ni2Cr alloys, Journal of Materials Science, 30, 4188 (1995).
  9. S. S. Kim, D. W. Kim, and Y. S. Kim, Primary water stress corrosion cracking (PWSCC) mechanism based on ordering reaction in Alloy 600, Metals and Materials International, 19, 969 (2013). Doi: https://doi.org/10.1007/s12540-013-5037-8
  10. H.S Chung, Utilization Research Planning Report for Kori unit 1(2016).
  11. S. S. Hwang, PWSCC of Alloy 600 components in PWRs-Part 1, Corrosion and Protection, 12, 1 (2013).