Optimizing asset management for Structure System Components of RSG-GAS: A reliability-centric approach

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-07-01 DOI:10.1016/j.net.2024.06.055
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Abstract

This study focuses on the Structure, System, and Components (SSC) of G.A Siwabessy Multipurpose Reactor (RSG-GAS), emphasizing the integration of reliability improvement within asset management optimization. The research aims to derive Maintenance Priority Index (MPI) values, contributing to system reliability ratings, crucial for assessing component functionality and estimating Remaining Useful Life (RUL) The methodology involves measuring critical aspects of system quality, safety, and cost. The MPI value, representing 10 % of SSC critical components, guides subsequent reliability calculations. Utilizing failure data from RSG-GAS components (2010–2018) and reactor core configurations (70th-96th core), SSC reliability is simulated using Monte Carlo simulation, with RUL based on real data. High MPI values are identified for critical components such as KBE01/AP01-02_B in the primary purification system, JE-01/AP01-02_A in the primary cooling system, and PA01-02/CR001_A in the secondary cooling system. Maintenance intervals of 100 days are recommended for KBE01/AP 01–02_B and JE-01/AP01-02_A, exceeding 50 % reliability, while PA01-02/CR001_A maintenance can extend to 75 days. Monte Carlo simulation results, with 1000 samples, closely align with real reliability values. The RUL result projects operational lifetimes of 225.6, 221.4, and 171.5 days for KBE01/AP 01–02_B, JE-01/AP01-02_A, and PA01-02/CR001_A components. This study improves asset management, offering practical insights for critical safety system component maintenance planning.
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优化 RSG-GAS 结构系统组件的资产管理:以可靠性为中心的方法
本研究侧重于 G.A Siwabessy 多用途反应堆(RSG-GAS)的结构、系统和组件 (SSC),强调在资产管理优化中整合可靠性改进。该研究旨在得出维护优先指数(MPI)值,为系统可靠性评级做出贡献,这对评估组件功能和估算剩余使用寿命(RUL)至关重要。MPI 值占 SSC 关键部件的 10%,为后续的可靠性计算提供指导。利用 RSG-GAS 组件(2010-2018 年)和反应堆堆芯配置(第 70-96 堆芯)的故障数据,使用蒙特卡罗模拟法模拟 SSC 可靠性,并根据真实数据计算 RUL。确定了关键组件的高 MPI 值,如一级净化系统中的 KBE01/AP01-02_B、一级冷却系统中的 JE-01/AP01-02_A 和二级冷却系统中的 PA01-02/CR001_A。建议 KBE01/AP 01-02_B 和 JE-01/AP01-02_A 的维护间隔为 100 天,可靠性超过 50%,而 PA01-02/CR001_A 的维护间隔可延长至 75 天。蒙特卡罗模拟结果(1000 个样本)与实际可靠性值非常接近。RUL 结果预测 KBE01/AP 01-02_B、JE-01/AP01-02_A 和 PA01-02/CR001_A 组件的运行寿命分别为 225.6 天、221.4 天和 171.5 天。这项研究改进了资产管理,为关键安全系统组件维护规划提供了实用的见解。
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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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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