Multi-dimensional condensation behavior during ingress of coolant event experiments for fusion reactors with TRACE code

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Shun Nukaga, Masahiro Furuya
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Abstract

An Ingress of Coolant (ICE) event is defined as the intrusion of high-temperature, high-pressure coolant water into the plasma chamber of a nuclear fusion reactor. This phenomenon constitutes a critical safety concern, as it has the potential to result in the release of radioactive materials into the surrounding environment. Consequently, a proper assessment of an ICE must be made in the design of fusion reactors. Prior to the construction of ITER, the Integrated ICE Facility was constructed at the Naka Laboratory of the Japan Atomic Energy Research Institute (JAERI) in Japan to validate the computational code for the pressure suppression system in ITER against the obtained experimental data. This study examined the Integrated ICE Facility utilizing the TRACE code for two wall-thermal boundary conditions. By comparing the calculated and experimental values, it was found that the TRACE code could adequately evaluate the injected flow rate and pressure inside the plasma chamber. The discrepancy was partly attributed to the number of cells required to capture multidimensional water levels. Furthermore, it was determined that the timestep size exhibited a close relationship with the pressure within the suppression tank.

Abstract Image

用TRACE程序研究了核聚变反应堆冷却剂进入过程中的多维冷凝行为
冷却剂进入(ICE)事件是指高温高压冷却剂水进入核聚变反应堆的等离子体室。这种现象构成了一个严重的安全问题,因为它有可能导致放射性物质释放到周围环境中。因此,在设计聚变反应堆时,必须对ICE进行适当的评估。在ITER建设之前,在日本原子能研究所(JAERI)的中实验室建造了综合ICE设施,以根据获得的实验数据验证ITER中压力抑制系统的计算代码。本研究利用TRACE代码对两种壁面-热边界条件下的集成ICE设施进行了检查。通过对计算值和实验值的比较,发现TRACE程序可以很好地计算等离子体腔内的注入流量和压力。这种差异部分归因于捕获多维水位所需的细胞数量。此外,还确定了时间步长与抑制槽内压力的密切关系。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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