Validation process against late phase conditions of the passive autocatalytic recombiner simulation code PARUPM as a standalone tool using experimental data from REKO-3 and THAI facilities

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-11-22 DOI:10.1016/j.nucengdes.2024.113722

Araceli Dominguez-Bugarin , Ernst-Arndt Reinecke , Gonzalo Jiménez , Miguel Ángel Jiménez , Sanjeev Gupta

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引用次数: 0

Abstract

In case of a nuclear accident with core damage in a light water reactor, the oxidation of the fuel cladding and other materials could lead to the release of combustible gases (H₂ and CO) to the containment building. To mitigate the potential risk of combustion of these gases, passive autocatalytic recombiners (PARs) have been installed in numerous nuclear reactors in Europe and worldwide. PARs recombine H₂ and CO with O₂ producing H₂O and CO₂, respectively, without an open flame.

PARUPM is a code that simulates the behaviour of PARs using a physicochemical model approach. In the framework of the AMHYCO project (EU-funded Horizon 2020 project), which seeks to advance the understanding and simulation capabilities to support the combustion risk management in severe accidents, the code has been extensively enhanced and developed to simulate PAR operation with H₂/CO/O₂/steam mixtures. Alongside these new capabilities, the code needed a new validation process.

In this paper, the process of validation of PARUPM as a standalone code is described. The validation for steady state conditions was achieved through comparison with REKO-3 experimental data while the transient conditions were compared with results obtained with the THAI test facility. A thorough analysis of the code capabilities was performed by comparing the numerical results with experimental data for a broad series of conditions, namely: a range of different input gas temperatures and concentrations, oxygen starvation, CO poisoning, etc.

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利用 REKO-3 和 THAI 设施的实验数据，对作为独立工具的被动自催化重组器模拟代码 PARUPM 的后期条件进行验证的过程

如果轻水反应堆发生堆芯损坏的核事故，燃料包壳和其他材料的氧化会导致可燃气体（H2 和 CO）释放到安全壳建筑中。为了降低这些气体燃烧的潜在风险，欧洲和全球许多核反应堆都安装了被动式自催化重组器（PAR）。PARUPM 是一种使用物理化学模型方法模拟 PARs 行为的代码。在 AMHYCO 项目（由欧盟资助的地平线 2020 项目）框架内，该代码得到了广泛的增强和开发，以模拟 PAR 在 H2/CO/O2/ 蒸汽混合物中的运行。本文介绍了 PARUPM 作为独立代码的验证过程。本文介绍了 PARUPM 作为独立代码的验证过程。稳态条件的验证是通过与 REKO-3 实验数据进行比较实现的，而瞬态条件的验证则是通过与 THAI 试验设备获得的结果进行比较实现的。通过将数值结果与一系列条件下的实验数据进行比较，对代码能力进行了全面分析，这些条件包括：一系列不同的输入气体温度和浓度、氧气饥饿、一氧化碳中毒等。

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.