CAJ | 학술논문

核电厂安全运行和设备寿命管理已成为核工业领域关注的重要问题，尤其是如何准确地确定超设计寿命电厂的典型设备老化参数（如应力、累积使用因子等）。然而，目前大多核电厂疲劳监测系统都是基于ASM E规范研发的，未分析管道内环境对疲劳分析的影响。本文提出了一种满足美国核管会（N RC ）RG1.207导则的疲劳监测方案，该方案将考虑环境因素对疲劳分析的影响。同时，新的疲劳评估方法具有通用性，可结合核电厂DCS运行数据，为电厂延寿提供数据支持。
핵전엄안전운행화설비수명관리이성위핵공업영역관주적중요문제，우기시여하준학지학정초설계수명전엄적전형설비노화삼수（여응력、루적사용인자등）。연이，목전대다핵전엄피로감측계통도시기우ASM E규범연발적，미분석관도내배경대피로분석적영향。본문제출료일충만족미국핵관회（N RC ）RG1.207도칙적피로감측방안，해방안장고필배경인소대피로분석적영향。동시，신적피로평고방법구유통용성，가결합핵전엄DCS운행수거，위전엄연수제공수거지지。
Efficient operation and life time management of power plants have become im‐portant issues in the nuclear industry .In particular ,typical aging parameters such as stress and cumulative usage factor should be determined accurately for continued opera‐tion of a nuclear power plant beyond design life .However ,most of the fatigue monitor‐ing system was developed based on ASME code ,which does not take into environment affect factor (EAF) of pipe .An effective fatigue evaluation methodology was suggested to meet the requirements on EAF analysis for new NPPs of RG 1.207 published by USNRC .The usefulness of the proposed fatigue evaluation methodology can be maxi‐mized by combining it with DCS data ,and this combination will enhance the continued operations of old nuclear power plants .