整体式压水堆安全壳和堆池模型的节点化研究

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-09 DOI:10.1016/j.anucene.2025.111866

Tuomo Sevón

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引用次数: 0

摘要

本研究采用MELCOR 2.2规范对小型整体式压水堆（iPWR）安全壳和反应堆池节点化的影响进行了研究。研究的重点是欧盟资助的SASPAM-SA项目的设计1，其特点是部分淹没在反应堆池中的安全壳。分析了两种事故情景：设计基础事故（DBA）和严重事故。模拟使用四种不同的节点化进行：详细的基本模型、单卷容器模型、单卷池模型以及用于容器和池的单卷模型。结果表明，虽然精细节化可以模拟温度分层，但其对整体事故模拟结果、压力和裂变产物释放的影响有限。研究结果表明，单体积节点化和更详细的节点化之间的差异相对较小，由于更有效的传热，详细的节点化在DBA场景中提供了稍低的密封压力。

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A nodalization study on modeling the containment and reactor pool of an integral PWR

This study investigates the impact of nodalization of the containment and reactor pool of a small integral Pressurized Water Reactor (iPWR) using the MELCOR 2.2 code. The research focuses on Design 1 of the EU-funded SASPAM-SA project, featuring a containment partially submerged in the reactor pool. Two accident scenarios were analyzed: a Design Basis Accident (DBA) and a severe accident. The simulations were conducted with four different nodalizations: a detailed base model, a single-volume containment model, a single-volume pool model, and a single-volume model for both the containment and the pool. The results indicate that while detailed nodalization can simulate temperature stratification, its effect on the overall accident simulation results, pressures and fission product releases is limited. The findings suggest that differences between single-volume and more detailed nodalizations are relatively small, with the detailed nodalization providing slightly lower containment pressures during the DBA scenario due to more efficient heat transfer.

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来源期刊

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.