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Current Status on the Development and Application of Fatigue Monitoring System for Nuclear Power Plants

원전 피로 감시 시스템 개발 및 적용 현황

  • Received : 2017.11.30
  • Accepted : 2017.12.19
  • Published : 2017.12.30

Abstract

Metal fatigue is an important aging mechanism that material characteristics can be deteriorated when even a small load is applied repeatedly. An accurate fatigue evaluation is very important for component structural integrity and reliability. In the design stage of a nuclear power plant, the fatigue evaluations of the Class 1 components have to be performed. However, operating experience shows that the design evaluation can be very conservative due to conservatism in the transient severity and number of occurrence. Therefore, the fatigue monitoring system has been considered as a practical mean to ensure safe operation of the nuclear power plants. The fatigue monitoring system can quantify accumulated fatigue damage up to date for various plant conditions. The purpose of this paper is to describe the fatigue monitoring procedure and to introduce the fatigue monitoring program developed by the authors. The feasibility of the fatigue monitoring program is demonstrated by comparing with the actual operating data and finite element analysis results.

세계적으로 원자력발전소의 안정적 운영 및 안전성 확보를 위해 수명기간 중 주요 기기 및 배관의 실제 운전 과도상태를 체계적으로 관리하고, 피로 손상의 정량적 평가 및 관리를 위한 체계적인 시스템이 요구되고 있는 실정이다. 이에 본 논문에서는 원자력발전소의 안전등급 1 설비에 대한 피로 평가요건을 분석하였고, 피로 감시방법 및 절차와 웹 기반으로 개발된 피로 감시 시스템인 NuFMS 개발 및 검증 내용을 기술하였다. NuFMS는 설계 시 고려한 과도상태 발생 횟수 대 비발전소의 특정 운전 시점에서의 실제 발생 횟수를 비교하여 안전 여유도의 정량적 확인이 가능하며, 누적피로사용계수 도출을 통해 정확한 피로영향 분석뿐만 아니라 손상 관리가 가능하다. 이와 같이 NuFMS의 적용을 통해 원자력발전소 기기 및 배관의 피로 건전성을 확인하고 운영 신뢰도를 향상시킬 수 있으며, 발전소의 안전성 유지 및 운영비용 절감 등의 효과를 기대할 수 있다. 따라서 향후 국내 전 원전에 NuFMS를 확대 적용할 예정이며, 이러한 기술의 해외 수출을 적극 추진 중이다.

Keywords

References

  1. ASME, 2013, Rule for Construction of Nuclear Power Plant Component, Sec. III, Div. 1.
  2. USNRC, 2010, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, NUREG-1800, Rev. 2.
  3. USNRC, 2010, Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2.
  4. EPRI, 1988, Fatigue-Pro: On-Line Fatigue Usage Transient Monitoring System, NP-5835.
  5. EPRI, 2001, User's Manual For Fatigue-Pro Version 3.0, Report No. 1002861.
  6. EPRI, 2011, Stress-Based Fatigue Monitoring: Methodology for Fatigue Monitoring of Class 1 Nuclear Components in a Reactor Water Environment, Report No. 1022876.
  7. Jouan, B., Berghols, S. and Rudolph, J., 2014, "Fatigue Monitoring Approaches for Power Plants," Proc. of ASME Pressure Vessels and Piping Conference, No. 28100.
  8. Cranford, E. L., 2009, "Fatigue Monitoring using WESTEMS with Automated Data Checking," Proc. of Nuclear Plant Fatigue Applications Workshop.
  9. Boo, M. H., Lee, K. S., Kim, H. S. and Oh, C. K., 2016, "Environmental Fatigue and Fatigue Monitoring System in Korea," Proc. of ASME Pressure Vessels and Piping Conference, No. 63374.
  10. KHNP, 2013, Fatigue Monitoring Method for Key Components and Piping of the Nuclear Power Plant, Topical Report.
  11. Shim, H. J., Oh, C. K., Kim, H. S., Boo, M. H. and Kwon, J. J., 2015, "New Approach for Fatigue Damage Monitoring based on Actual Operating History of Nuclear Power Plant," Nuclear Technology, Vol. 190, pp. 88-96. https://doi.org/10.13182/NT13-150
  12. Boo, M. H., Oh, C. K., Kim, H. S. and Choi, C. R., 2017, "Numerical Simulation of Temperature and Thermal Stress for Nuclear Piping by Using Computational Fluid Dynamics Analysis and Green's Function," Journal of Mechanical Science and Technology, Vol. 31, No. 5, pp. 2243-2249. https://doi.org/10.1007/s12206-017-0421-9
  13. Kuo, A. Y., Tang, S. S. and Riccardella, P. C., 1986, "An On-line Fatigue Monitoring System for Power Plant: Part I - Direct Calculation of Transient Peak Stress through Transfer Matrices and Green's Functions," Proc. of ASME Pressure Vessels and Piping Conference, Vol. 112.
  14. US Nuclear Regulatory Commission, 2014, Effect of LWR Coolant Environments on Fatigue Life of Reactor Materials, NUREG/CR-6909, Rev. 1.