Validation of the PARUPM and GOTHIC 8.3 code coupling using THAI hydrogen recombination tests

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Araceli Domínguez-Bugarín , Carlos Vázquez-Rodríguez , Luis Serra , Stephan Kelm , Ernst-Arndt Reinecke , Gonzalo Jiménez , Miguel Ángel Jiménez , Sanjeev Gupta
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Abstract

In case of a severe accident in a nuclear power plant (NPP), large amounts of H2 and CO could be generated, potentially leading to uncontrolled combustion if concentrations within the flammability thresholds are reached. To mitigate this hazard, many NPPs equipped their containment buildings with passive autocatalytic recombiners (PARs). Thus, there is an interest in the developing of mechanistic models capable of predicting the behaviour of these devices.
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), the code has been validated as a standalone tool using experimental data. Nevertheless, the containment thermal hydraulics have a significant impact on the PAR behaviour, thus, in a next phase, PARUPM has been integrated as an add-on program within the thermohydraulic simulation code, GOTHIC.
The present paper provides an overview of the capabilities of the joint simulation with PARUPM – GOTHIC 8.3. This coupling enables a detailed simulation of the recombination process under dynamically evolving conditions, allowing to represent the feedback between the PAR and the containment atmosphere. The validation was conducted based on a sequence of experiments on H2 recombination by PARs performed at the THAI experimental facility. The results of these simulations confirm that the coupled PARUPM-GOTHIC model can predict the behaviour of PARs in full containment scenarios while maintaining low computational efforts, making the tool suitable for detailed safety analysis and scalable for full-containment simulations involving multiple recombiners.
使用THAI氢复合试验验证PARUPM和GOTHIC 8.3代码耦合
在核电站(NPP)发生严重事故的情况下,可能会产生大量的H2和CO,如果达到可燃性阈值内的浓度,可能导致不受控制的燃烧。为了减轻这种危险,许多核电站为其安全壳建筑配备了被动自催化重组器(par)。因此,人们对开发能够预测这些装置行为的机械模型很感兴趣。PARUPM是一种使用物理化学模型方法模拟par行为的代码。在AMHYCO项目(欧盟资助的Horizon 2020项目)的框架内,该代码已使用实验数据作为独立工具进行了验证。然而,安全壳热工力学对PAR的性能有重大影响,因此,在下一阶段,PARUPM已作为附加程序集成到热水力模拟代码GOTHIC中。本文概述了PARUPM - GOTHIC 8.3的联合仿真能力。这种耦合可以在动态变化的条件下详细模拟重组过程,从而可以表示PAR和容器气氛之间的反馈。该验证是基于在泰国实验设施进行的par对H2重组的一系列实验进行的。这些模拟结果证实,耦合PARUPM-GOTHIC模型可以在保持低计算量的情况下预测全密封情况下par的行为,使该工具适用于详细的安全分析,并可扩展到涉及多个重组器的全密封模拟。
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
Annals of Nuclear Energy
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.
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