DOI QR코드

DOI QR Code

Development of an Integrity Evaluation System (WIES) for Fuel Channels in CANDU Reactors

중수로 연료관 건전성 평가시스템(WIES) 개발

  • Choi, Sung-Nam (Nuclear Power Lab., Korea Electric Power Research Institute) ;
  • Kim, Hyung-Nam (Nuclear Power Lab., Korea Electric Power Research Institute) ;
  • Yoo, Hyun-Joo (Nuclear Power Lab., Korea Electric Power Research Institute) ;
  • Kwon, Dong-Kee (Wolsong 1 Nuclear Power Plant, Korea Hydro & Nuclear Power) ;
  • Hwang, Won-Gul (School of Mechanical Systems Engineering, Chonnam Nat'l Univ.)
  • Received : 2010.05.11
  • Accepted : 2010.07.14
  • Published : 2010.09.01

Abstract

Pressure tubes at the CANada Deuterium Uranium (CANDU) nuclear power plants are periodically inspected in accordance with the CSA N285.4 code. If flaws that do not satisfy the criteria given in CSA N285.4 are detected, the code permits a fitness-for-service assessment to determine the acceptability of the flawed pressure tubes. In this paper, the Wolsong In-service Evaluation System (WIES) is introduced; this system has been developed for the assessment of the flawed pressure tubes and is based on CSA N285.8. Since the system evaluates the integrity of flawed pressure tubes exactly and promptly during an in-service inspection, it will help in operating the Wolsong nuclear power plants without prolonging the outage period.

가압중수로 연료관은 CSA N 285.4 기술기준에 따라 주기적인 가동중검사가 수행되고 있다. 가동중검사시 발견된 결함이 CSA N 285.4 의 허용기준을 초과하는 경우, 결함 연료관의 계속 운전을 위해 가동적합성 평가를 허용하고 있다. 캐나다 COG(CANDU Owner's Group)를 중심으로 중수로 연료관의 결함 건전성 평가 기술기준인 CSA N285.8 이 개발되었다. 본 논문에서는 CSA N285.8 을 기반으로 연료관의 건전성 평가시스템 WIES(Wolsong In-service Evaluation System)를 개발 하였다. 중수로 연료관의 가동중검사시 결함이 발견되는 경우, 개발된 시스템은 신속하고 정확한 건전성 평가를 수행하여 계획예방 정비기간의 연장을 방지하여 원전 이용률 향상에 기여할 것으로 판단된다.

Keywords

References

  1. CAN/CSA, 1994, "Periodic Inspection for CANDU Nuclear Power Plant Components," N285.4-94
  2. CANDU Owners Group, 1996, "Fitness-for-Service Guidelines for Zirconium Alloy Pressure Tubes in Operating CANDU Reactors," COG-91-66
  3. CSA, 2005, "Technical Requirements for In-Service Evaluation of Zirconium Alloy Pressure Tubes in CANDU Reactors," N285.8-05
  4. Raju, I. S. and Newman, J. C., 1982, "Stress Intensity Factors for Internal and External Surface Cracks in Cylinder Vessels," Journal of Pressure Vessel Technology, Vol. 104, pp. 293-298 https://doi.org/10.1115/1.3264220
  5. AECL, 2004, "Results from the Analysis of Wolsong Unit 1 Scrap Sampling from 2004 May," 59-31100- TR-001, Rev. 0
  6. AECL, 2008, "Fuel Channel Stress Report Wolsong 1 Retubing Project," 59RF-31100-SR-001, Rev. 1
  7. AECL, 1996, "Wolsung-234 Nuclear Power Plant Fuel Stress Analysis," 86-31100-SR-001
  8. Choi, Y. H., 2002, "CANDU Pressure Tube Integrity Evaluation System (PTIES)," KINS/RR-170, KINS