Evaluation of a hybrid in-vessel retention strategy with ex-vessel cooling for APR1400 under extended station blackout conditions

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-09-21 DOI:10.1016/j.nucengdes.2024.113600
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Abstract

The purpose of this study is to examine the success window of a hybrid in-vessel retention (IVR) strategy coupled with ex-vessel cooling (ERVC) under an extended Station Blackout (SBO). The high-power-density reactor, APR-1400, is selected and modelled using the computer code ASYST, to examine the thermal–hydraulic response and evaluate the efficacy of a hybrid IVR-ERVC strategy as the accident progresses. Specifically, the hybrid IVR-ERVC strategy refers to combining in-vessel injection as well as ex-vessel cooling to maintain the vessel integrity. Naturally, depressurization of the pressure vessel, which is a precursor to the in-vessel injection, is also applied. The hybrid IVR-ERVC strategy is meant to mitigate the accident and prevent a vessel breach using a set of operator actions within the framework of severe accident management guidelines (SAMG), capitalizing on the portable equipment of the Diverse and Flexible (FLEX) strategy. Three high level candidate actions (HLCAs), namely primary-side depressurization and in-vessel injection along with ex-vessel cooling via cavity flooding are systematically implemented to assess their effectiveness in maintaining the vessel’s integrity for a mission time of 72 h. By combining those high level actions, the corium can be cooled both internally as well as externally to avoid the critical heat flux bottleneck.

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评估在长期停电条件下为 APR1400 采用的混合舱内保留和舱外冷却策略
本研究的目的是考察在延长的电站停电(SBO)条件下,结合舱外冷却(ERVC)的混合舱内滞留(IVR)策略的成功窗口。本研究选择了高功率密度反应堆 APR-1400,并使用计算机代码 ASYST 对其进行建模,以检查热-水力响应,并评估随着事故的发展 IVR-ERVC 混合策略的有效性。具体来说,IVR-ERVC 混合策略指的是将舱内注入和舱外冷却相结合,以保持容器的完整性。当然,压力容器的减压也会应用,这是容器内喷射的前奏。IVR-ERVC 混合策略旨在利用多样化和灵活(FLEX)策略的便携式设备,在严重事故管理准则(SAMG)的框架内通过一系列操作员行动来缓解事故并防止容器破裂。系统地实施了三项高级候选行动(HLCAs),即一次侧减压和容器内注入以及通过空腔充水进行容器外冷却,以评估它们在 72 小时任务时间内保持容器完整性的有效性。
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
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.
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