Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept

H. Yada, S. Takaya, K. Morohoshi, Shinobu Yokoi
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Abstract

In order to develop rationalized maintenance plans of nuclear power plants, it is necessary to consider characteristics of each plant. For sodium-cooled fast reactor (SFR) plants, there are constraints on inspections due to the specialty that sodium equipment needs to be handled, which is one of the important points when considering rationalization of maintenance. Therefore, we previously proposed a maintenance optimization scheme based on the System Based Code (SBC) concept. The concept of the SBC intends to give a theoretical procedure to optimize the reliability of the system by administrating every related engineering requirement throughout the life of the system from design to decommissioning. “ASME Boiler and Pressure Vessel Code, Code Case, N-875 Alternative Inservice Inspection Requirements for Liquid-Metal Reactor Passive Components” was already developed based on the SBC concept. The basic procedure of the code case has been also implemented in “ASME Boiler and Pressure Vessel Code, Section XI, Division 2” which provides requirements for Reliability and Integrity Management (RIM) programs for nuclear power plants including advanced reactors. One of proposed scheme goals is to develop detailed procedures of preparing a maintenance plan based on the process in the code case. In this study, the procedures to determine inspections for potential degradation and additional inspections in terms of defense-in-depth have been further clarified. The modified maintenance optimization scheme consists of the following processes. At first, potential active degradation mechanisms are identified. If there are any degradation mechanisms that are not addressed in the design codes, structural reliability evaluations are conducted to confirm whether the component of interest has sufficient reliability for the degradation mechanisms of concern. In the case the evaluated reliability does not meet a predetermined reliability target, inspections for the potential degradation are required. Next, the detectability of hypothetical defects before they grow to an unacceptable size in terms of plant safety is assessed. A method which has sufficient detectability, either in direct way such as volumetric examinations or in indirect way such as monitoring, is required as an additional inspection. If any methods are not applicable, reliability evaluation with a penalty is required. The penalty is determined conservative hypothesis relating safety function of the component of interest. If the evaluated reliability meets to the reliability target, additional inspections can be exempted. In this paper, the modified maintenance optimization scheme is also illustrated by a quantitative trial evaluation of the core support structure of the next SFR under development in Japan.
基于系统代码概念确定合理在役检验需求的详细流程
为了制定合理的核电站维修计划,必须考虑各核电站的特点。对于钠冷快堆(SFR)电站来说,由于钠设备需要处理的特殊性,在检查方面存在制约,这是考虑维护合理化的重要问题之一。因此,我们先前提出了一种基于系统基于代码(System based Code, SBC)概念的维护优化方案。SBC的概念旨在通过管理系统从设计到退役的整个生命周期中的每一个相关工程要求,给出一个优化系统可靠性的理论程序。“ASME锅炉和压力容器规范,规范案例,N-875液态金属反应堆无源部件在役替代检验要求”已经根据SBC概念制定。建议的方案目标之一是根据代码案例中的过程,开发准备维护计划的详细过程。在本研究中,进一步阐明了确定对潜在退化进行检查和在纵深防御方面进行额外检查的程序。修改后的维护优化方案包括以下步骤。首先,确定了潜在的主动降解机制。如果存在设计规范中未涉及的退化机制,则进行结构可靠性评估,以确认感兴趣的组件是否具有足够的可靠性来处理所关注的退化机制。当评估的可靠性不满足预定的可靠性目标时,需要对潜在的退化进行检查。接下来,在假设的缺陷发展到不可接受的规模之前,对其在工厂安全方面的可检测性进行评估。作为额外的检查,需要一种具有足够可检测性的方法,无论是直接方式,如容积检查还是间接方式,如监测。如果任何方法都不适用,则需要进行带有惩罚的可靠性评估。惩罚是与利益成分的安全函数有关的保守假设确定的。如果评估的可靠性达到了可靠性目标,则可以免除额外的检查。本文还通过对日本正在研制的新型SFR核心支撑结构的定量试验评价来说明改进后的维修优化方案。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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