상부 탑재형 노내계측기 노즐의 환경피로평가
Environmental Fatigue Evaluation of Top-Mounted In-Core Instrumentation Nozzle
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초록
상부 탑재형 노내계측기(TM-ICI) 개발은 원자로하부헤드 대신 원자로상부헤드로 계측기를 삽입함으로써 중대사고 위험을 줄이기 위해 진행 중이다. 이 개발 과제의 일환으로, NUREG/CR-6909와 Code Case N-761의 두 방법에 따라 TM-ICI 노즐에 대한 환경피로평가가 수행되었다. TM-ICI 노즐은 level A, level B 및 시험 조건에서의 과도조건에 따른 하중을 받는데 이에 대해 피로평가를 해야 한다. 원자로냉각재환경이 고려된 TM-ICI 노즐의 누적사용계수는 1이하로 평가되었고, 이는 ASME Code 허용기준을 만족한다.
Abstract
The development of Top-Mounted In-Core Instrumentation(TM-ICI) is an ongoing project to reduce the risk due to severe accidents by inserting the instrumentation into a reactor closure head instead of a reactor bottom head. As part of this project, environmental fatigue analyses for TM-ICI nozzle have been performed using two methods of NUREG/CR-6909 and Code Case N-761. TM-ICI nozzle is subjected to transient loads for level A, level B and test conditions that should be evaluated for a fatigue analysis. It is found that a cumulative usage factor considering reactor coolant environment for TM-ICI nozzle is evaluated as less than 1, which is ASME Code allowable criteria of a fatigue analysis.
참고문헌 (10)
- American Society of Mechanical Engineers, "ASME Boiler and Pressure Vessel Code-An International Code", Section Ⅱ, Part D and Section Ⅲ, Division 1–Subsection NB and Appendices, ~ (2015)
- ANSYS Finite Element Program, "ANSYS Mechanical APDL, Version 15.0, ANSYS Inc.", ~ (2014)
- Armin, R., "Environmental Influences on the Fatigue Assessment of Austenitic and Ferritic Steel Components including Welds", Proc. ASME 2014 Press. Vessels & Pip. Div. Conf. (2014)
- Case of ASME Bolier and Pressure Vessel Code, "Fatigue Design Curves for Light Water Reactor (LWR) Environments", Code Case N-761, ~ (2010)
- Frank, K., "Principles of Heat Transfer", pp.475~ (1993), West Publishing Company
- 이연주, "노심용융사고 시 관통노즐이 제거된 원자로용기 하부헤드의 구조 건전성 평가", 한국전산구조공학회논문집, 27(3), pp.191~198 (2014), 한국전산구조공학회[DOI]
- Mark, A. G., "Strain Rate Calculation Approach in Environmental Fatigue Evaluations", J. Press. Vessel Tech., 136, pp.045001-1~045001-5 (2014)
- Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, "Omesh, C.", Argonne National Laboratory, ~, pp.NUREG (2014), CR-6909
- Seiji, A., "Environmental Fatigue Evaluation for Class 1Components of an Advanced PWR", Pro. ASME 2014 Press. Vessels & Pip. Div. Conf. (2014)
- U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research, "Guidelines for Evaluating the Effects of Light-Water Reactor Coolant Environments in Fatigue Analyses of Metal Components, Regulatory Guide 1.207, Rev. 1(Draft DG-1309), Section C", ~ (2014)
