Environmental Fatigue Evaluation of Top-Mounted In-Core Instrumentation Nozzle

Yoon Hyo-Sub; Kim Jong-Min; Maeng Cheol-Soo; Kim Gee-Seok; Kim Hyun-Min

doi:10.7734/COSEIK.2016.29.3.245

All Issue

2016 Vol.29, Issue 3 Preview Page Next Page

Environmental Fatigue Evaluation of Top-Mounted In-Core Instrumentation Nozzle 상부 탑재형 노내계측기 노즐의 환경피로평가

2016. pp. 245-252

PDF XML

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.

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.

Keywords

reactor pressure vessel, top-mounted in-core instrumentation nozzle, environmental fatigue evaluation

원자로 압력용기, 상부 탑재형 노내계측기 노즐, 환경피로평가

References

American Society of Mechanical Engineers2015 EditionASME Boiler and Pressure Vessel Code-An International Code, Section Ⅱ, Part D and Section Ⅲ, Division 1-Subsection NB and Appendices.

ANSYS Finite Element Program2014ANSYS Mechanical APDL Version 15.0ANSYS Inc.

Armin R. Matthias H. Jürgen R. Paul W. 2014Environmental Influences on the Fatigue Assessment of Austenitic and Ferritic Steel Components including WeldsProc. ASME 2014 Press. Vessels & Pip. Div. Conf.PVP2014-28728California29

Case of ASME Bolier and Pressure Vessel Code2010Code Case N-761.

K., Frank and S.B., Mark, 1993. Principles of Heat Transfer. West Publishing Company, Fifth edition, p.475.

Y.J., Lee, J.M., Kim, H.M., Kim, D.H., Lee and C.K., Chung, 2014. Structural Integrity Evaluation of Reactor Pressure Vessel Bottom Head without Penetration Nozzles in Core Melting Accident. J. Comput. Struct. Eng. Inst. Korea, 27, pp.191-198.

10.7734/COSEIK.2014.27.3.191

A.G., Mark, C.S., Matthew, H.R., David and C., E. Lyles, 2014. Strain Rate Calculation Approach in Environmental Fatigue Evaluations. J. Press. Vessel Tech., 136, p.045001-1~5..

10.1115/1.4026113

Omesh C. Gray L.S. 2014Effect of LWR Coolant Environments on the Fatigue Life of Reactor MaterialsArgonne National LaboratoryNUREG/ CR-6909Rev. 1(Draft), App. A and C.

Seiji A. Kunimitsu T. Masanori T. 2014Environmental Fatigue Evaluation for Class 1 Components of an Advanced PWRPro. ASME 2014 Press. Vessels & Pip. Div. Conf.PVP2014-28300California

U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research2014Guidelines for Evaluating the Effects of Light-Water Reactor Coolant Environments in Fatigue Analyses of Metal ComponentsRegulatory Guide 1.207Rev. 1(Draft DG-1309)Section C

Information

Publisher :Computational Structural Engineering Institute of Korea
Publisher(Ko) :한국전산구조공학회
Journal Title :Journal of the Computational Structural Engineering Institute of Korea
Journal Title(Ko) :한국전산구조공학회 논문집
Volume : 29
No :3
Pages :245-252
Received Date : 2016-03-28
Revised Date : 2016-05-10
Accepted Date : 2016-05-18
DOI :https://doi.org/10.7734/COSEIK.2016.29.3.245

Journal of the Computational Structural Engineering Institute of Korea ISSN:1229-3059(Print) 2287-2302(Online) 한국전산구조공학회 논문집

All Issue