Research on simulation of hydrogen diffusion behavior based on CONTHAC-3D code

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

Annals of Nuclear Energy Pub Date : 2024-10-28 DOI:10.1016/j.anucene.2024.111003

Yuan Chang , Hui Wang , Gong-Lin Li , Ming Ding

引用次数: 0

Abstract

An in-house code called CONTHAC-3D was developed to investigate the fundamental thermal–hydraulic phenomena occurred in the containment under severe accidents for NPPs. The code included specific models to simulate the special systems of HPR1000 and ACP100. The classical backward-facing step flow benchmark and BMC HYJET helium jet experiments were selected to investigate the code’s capability of simulating hydrogen diffusion process. The results showed that the difference between the calculated and experimental results could be negligible. The code was then applied to investigate hydrogen diffusion and distribution for HPR1000. The results showed that the hydrogen released from the break rises vertically and rapidly to the containment dome, then the gas diffused into the dome and lower compartments. As the time went by, the hydrogen concentration in lower compartments seemed to be higher than that in the containment dome. The results could provide foundation for the arrangement of hydrogen risk mitigation measures.

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基于 CONTHAC-3D 代码的氢扩散行为模拟研究

开发了名为 CONTHAC-3D 的内部代码，用于研究核电站严重事故情况下安全壳内发生的基本热液现象。该代码包括用于模拟 HPR1000 和 ACP100 特殊系统的特定模型。选择了经典的后向阶梯流基准和 BMC HYJET 氦射流实验来考察代码模拟氢扩散过程的能力。结果表明，计算结果和实验结果之间的差异可以忽略不计。随后，该代码被用于研究 HPR1000 的氢扩散和分布。结果表明，从破裂处释放的氢气垂直快速上升到安全壳穹顶，然后气体扩散到穹顶和下层舱室。随着时间的推移，下层舱室的氢气浓度似乎高于安全壳穹顶的氢气浓度。这些结果可为氢风险缓解措施的安排提供依据。

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 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.