对 CFETR 失真空事故中的破损情况进行参数研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chenxi Hu , Shanliang Zheng , Yuanjie Li
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引用次数: 0

摘要

在中国聚变工程试验堆(CFETR)中,发生失真空事故(LOVA)可能导致高速气流进入真空容器,造成等离子体破坏,并可能带来重大安全隐患。本研究利用 ANSYS Fluent 软件,通过建模和仿真分析了涉及 CFETR 真空容器 (VV) 中多个微小破口的 LOVA。研究在数值模型验证的基础上,考察了真空容器中的初始压力、破损点的总面积、数量、位置和分布对 LOVA 期间气体流动特性的影响。分析包括研究超音速流体在 LOVA 条件下产生的马赫盘的演变和消失。在总面积不变的情况下,明显断裂点数量的增加将导致喷流临界质量流速的降低。这种降低会减缓流速的下降,从而延长必要的稳定时间。此外,研究结果表明,随着断裂点数量的增加,沿中心流轴观察到的马赫盘的大小会减小,而数值则呈现上升模式。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Parametric study of the breaking scenarios during the loss of vacuum accident for CFETR
In the China Fusion Engineering Test Reactor (CFETR), the occurrence of a Loss of Vacuum Accident (LOVA) could result in high-velocity airflow entering the vacuum vessel, causing plasma disruption and potentially posing a significant safety hazard. In this study, the LOVA involving multiple small and minor breaches in the vacuum vessel (VV) of the CFETR is analyzed through modeling and simulation utilizing the ANSYS Fluent software. The study examines the influence of the initial pressure in VV, the total area, number, position, and distribution of breaking points on gas flow characteristics during the LOVA, based on the validation of the numerical model. The analysis includes the examination of the evolution and disappearance of the Mach disk resulting from supersonic fluid under the conditions of LOVA. With a constant total area, an increase in the number of distinct breaking points would result in a reduction of the critical mass flow rate of the jet. This decrease would decelerate the decline of the flow rate, consequently extending the necessary stability time. Moreover, the findings indicate that as the number of breaking points increases, the size of the Mach disk observed along the central flow axis diminishes, while the numerical value demonstrates a rising pattern.
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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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