Impact assessment of the integration of a generic PEM electrolyser facility into Rivne nuclear station

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-06 DOI:10.1016/j.nucengdes.2024.113767
Eduard Diaz-Pescador, Marco Viebach, Florian Gamaleja, Wolfgang Lippmann, Antonio Hurtado
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Abstract

This manuscript presents the outcomes from the impact assessment applied to the onsite integration of a 40 MW hydrogen production plant (HPP) into the protected area of Rivne nuclear power plant (NPP) in Ukraine. The scope of this work is limited to frequency estimation and blast loading characterization applied to three cases of study, representative of the worst-case scenario at different HPP locations. In the framework of the Euratom NPHyCo project, the NPP operator has proposed integration locations and provided corresponding distances to nearby structures with corresponding fragility criteria. The presented study assumes HPP operation at full capacity with allocated NPP electricity as a feedstock.
Hazardous points within the HPP are identified through HAZID (HAZard IDentification) methodology, which is assisted with system reliability analysis based on component failure rates. The identification of accident sequences in the HPP and frequency estimation is accomplished by means of event tree analysis (ETA). The study identifies as the worst-case scenario within the HPP a hydrogen explosion due to the destructive potential over far-range distances via shock wave propagation. In the electrolyser system, an unintended release of hydrogen may trigger a vapour cloud explosion (VCE), whereas in the adjacent hydrogen buffer tank a physical explosion may trigger a shock wave with subsequent projectile generation. The results show that the highest frequency of a hydrogen VCE is in the order of 10-7 per year following a 1% leak in the separator vessel upstream flange within the gas processing area.
The blast load characterization shows that a hydrogen VCE within the electrolyser facility would not exceed the 10 kPa fragility criterion of nearby safety-related structures. Contrarily, a physical explosion in the 30 kg buffer tank may lead to projectile generation with the potential to reach the standby diesel generators, cooling towers, and turbine building at a distance up to 500 m. The vessel fragments are deemed as soft missiles with high deformability upon impact. Nevertheless, means of protection are proposed to reduce the risk of the coupled facility. The outcomes of the study are meant as recommendations for a subsequent comprehensive safety assessment by the NPP operator.
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通用PEM电解槽设施与Rivne核电站整合的影响评估
本文介绍了乌克兰Rivne核电站(NPP)保护区40 MW制氢厂(HPP)现场整合影响评估的结果。这项工作的范围仅限于频率估计和爆炸载荷特征,应用于三个研究案例,代表了不同HPP位置的最坏情况。在Euratom NPHyCo项目的框架内,核电站运营商提出了集成位置,并提供了与附近结构的相应距离和相应的脆弱性标准。本研究假设HPP以分配的NPP电力为原料满负荷运行。HPP中的危险点通过HAZID(危险识别)方法进行识别,该方法借助于基于组件故障率的系统可靠性分析。通过事件树分析(ETA)实现了HPP中事故序列的识别和频率估计。该研究确定了HPP内最坏的情况是氢气爆炸,这是由于通过冲击波传播的远距离破坏性潜力。在电解槽系统中,氢的意外释放可能引发蒸气云爆炸(VCE),而在相邻的氢缓冲罐中,物理爆炸可能引发冲击波,随后产生弹丸。结果表明,氢气VCE的最高频率为每年10-7次,在气体处理区内的分离容器上游法兰泄漏为1%。爆炸载荷表征表明,电解槽设施内的氢气VCE不会超过附近安全相关结构的10 kPa易碎性标准。相反,30 公斤缓冲罐的物理爆炸可能导致弹丸产生,并有可能到达备用柴油发电机、冷却塔和涡轮机建筑,距离可达500 米。舰船破片被认为是一种软导弹,在撞击时具有很高的变形能力。然而,提出了保护措施,以减少耦合设施的风险。该研究的结果将作为NPP运营方随后进行综合安全评估的建议。
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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