Thermal-hydraulic analysis of temporary spent fuel storage in the upper pool of the Kuosheng units under postulated leakage accident

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-10-07 DOI:10.1016/j.nucengdes.2025.114527

Yen-Shu Chen

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引用次数: 0

Abstract

Two BWR/6 units at the Kuosheng Nuclear Power Plant are undergoing decommissioning. Since 2018, the cask loading pool (CLP), which is a sub-pool of the spent fuel pool (SFP), has been used for spent fuel storage. To prepare for the implementation of a dry-cask storage facility, the plant has committed to restore the CLP to its original state. During the recovery period, the assemblies stored in the CLP must be temporarily moved to the upper pool (UP), which is a part of the Mark III containment. In this study, a thermal–hydraulic model has been developed using the GOTHIC code for the analysis of postulated leakage accidents. Effects of the leakage size, UP spray mitigation, reactor building (RB) modeling, and higher decay power are investigated. While the large leakage results in faster water inventory loss, it also promotes earlier air circulation in the fuel region to suppress the fuel temperature rise. The Kuosheng plant has installed spray mitigation above the UP, and the calculation results show that the spray effect can sufficiently prevent the fuel from being overheated. Three-dimensional RB modeling demonstrates good air mixing within this space. Additionally, cases with higher decay power are calculated. The availability of spray mitigation ensures the maintenance of fuel integrity.

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假定泄漏事故下阔胜机组上池临时乏燃料库热水力分析

Kuosheng核电站的两个BWR/6机组正在进行退役。自2018年以来，作为乏燃料池（SFP）的子池的桶装载池（CLP）已被用于乏燃料储存。为准备实施干桶贮存设施，该工厂已承诺将中电湾恢复到原来的状态。在恢复期间，存储在CLP中的组件必须临时移动到上池（UP），这是Mark III安全壳的一部分。在这项研究中，利用哥特代码建立了一个热-水力模型来分析假定的泄漏事故。研究了泄漏尺寸、UP喷雾缓解、反应堆建造（RB）模型和更高的衰变功率的影响。大的泄漏量在导致水库存损失加快的同时，也促进了燃油区域空气的早期循环，从而抑制燃油温度的升高。国胜电厂在UP上方安装了喷雾缓解装置，计算结果表明，喷雾效果能充分防止燃料过热。三维RB模型显示了该空间内良好的空气混合。此外，还计算了具有较高衰减功率的情况。喷雾缓解的可用性确保了燃料完整性的维护。

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 Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.