PSA level 1 analysis by considering redundancy and diversity of emergency diesel generators for APR-1400

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Muhammad Zubair, Ronak Shahin Radkiany, Mahra Mohammad Aljaradi, Shamma Abdulla Alblooshi, Horeya Sultan Alhammadi, Yumna Akram
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引用次数: 0

Abstract

This paper builds upon the initial Level 1 Probabilistic Safety Assessment (PSA) for Emergency Diesel Generator (EDG) failures in the APR-1400 Nuclear Power Plant (NPP). By incorporating more complex EDG failure scenarios and expanding the scope of fault trees and event trees, it provides a more comprehensive safety performance analysis using AIMS-PSA software. The results highlight the reactor’s safety systems’ resilience in the face of an increasing number of malfunctioning EDGs. An in-depth understanding of the interdependencies and failure probability of the Essential Chilled Water System (ECWS), Component Cooling Water System (CCWS), 480 V bus, and fault trees for the 125 V and 4.16 kV buses has been obtained through this detailed examination. The Core Damage Frequency (CDF) values from the analysis, 1.71E-6 /RY, were found to be significantly lower compared to official literature values of 2.56E-6 /RY and 2.25E-6 /RY, attributed to the exclusion of more extensive operational and environmental aspects of LOOP and common cause failure events. The findings provide critical insights for enhancing nuclear safety frameworks and underscore the need for scenario-based PSAs to address potential vulnerabilities. Overall, the paper not only effectively measures the resilience of the NPP’s safety measures to various failure modes but also provides regulators and plant management with insightful information about the significance of redundancy and diversity in preserving nuclear safety over the NPP’s operational lifetime.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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