Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Material degradation and its management of reactor internals in PWR

원자로 내부구조물 재료열화이력 및 관리방안

  • 황성식 (한국원자력연구원) ;
  • 김성우 (한국원자력연구원, 원자력재료안전연구부) ;
  • 김동진 (한국원자력연구원, 원자력재료안전연구부) ;
  • 최민재 (한국원자력연구원, 원자력재료안전연구부) ;
  • 임연수 (한국원자력연구원, 원자력재료안전연구부)
  • Received : 2016.04.04
  • Accepted : 2016.06.20
  • Published : 2016.06.30
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Abstract

The number of nuclear power plants operating in Korea was 24 as of year 2015. Nine units out of 24 units have been operated for a period over 20 years. Kori unit 1 has been in operation for 40 years, and an extended operation for Wolsong unit 1 was decided in 2015. There has been reported some crackings in reactor internals in PWR have been reported in Europe, USA, Japan and Korea, and some of them were replaced with new one. Repair and replacement technologies for the reactor internals have been developing in order to meet the regulatory requirements for long term operation in Korea. The technologies will also be used for the exported nuclear units. It is required to review degradation history of the reactor internals worldwide as a part of the degradation management program development. Schematics of reactor internals designed and supplied by Westinghouse, Framatome and Combustion Engineering are described herein. Materials degradation history of reactor internals of PWR plants in USA, Japan and Europe is surveyed and summarized. Some events from Korean plants are also described. Aging management strategy for the internals is suggested.

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References

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