SMR安全壳极限承压能力的数值研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Min Jeong Park , Han-Sang Woo , Dong-Hyeon Choi, Yoon-Suk Chang
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引用次数: 0

摘要

安全壳结构是确保核电站安全的重要组成部分,在严重的事故诱发条件下防止放射性物质的释放。随着小型模块化反应堆在全球范围内的发展,钢制安全壳已经取代了传统的安全壳建筑,需要建立新的安全评估方法。本研究利用ABAQUS有限元分析软件,对创新型SMR (i-SMR)钢CV的极限承压能力(UPC)进行了评估。通过比较不同位置的UPCs,用方程提出了自由场面积。通过最大主应变、环应变和膜应变,提出了最适宜的应变参数。此外,还评估了在假定的严重事故诱发条件下的温度效应和屈曲起爆压力。研究结果不仅为i-SMR提供了一种综合的UPC评估方法,也为使用钢CV的先进反应堆提供了一种综合的UPC评估方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Numerical investigation on ultimate pressure capacity of a SMR containment vessel
The containment structure is a vital component ensuring the safety of nuclear power plants by preventing the release of radioactive materials under severe accident-induced conditions. As small modular reactors (SMRs) have been developing globally, steel containment vessels (CVs) have replaced conventional containment buildings and new assessment method should be established with regard to safety. In this study, ultimate pressure capacity (UPC) was assessed for the Innovative SMR (i-SMR) steel CV by using the finite element analysis software ABAQUS. Free-field areas were proposed with equations, through comparisons of UPCs at different locations. By using maximum principal, hoop, and membrane strain, the most appropriate strain parameter was suggested. Furthermore, temperature effect under the postulated severe accident-induced condition and buckling initiation pressure were assessed. The findings provide a comprehensive methodology for assessing the UPC of not only for the i-SMR but also for the advanced reactors utilizing steel CV.
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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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