用于研究线性等离子体发生器 Magnum-PSI 中蒸汽屏蔽性能和锂传输的锂蒸汽箱分流器模块设计

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
F. Romano , V.F.B. Tanke , J.A. Schwartz , S. Brons , R.J. Goldston , T.W. Morgan
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引用次数: 0

摘要

蒸气箱分流器概念旨在处理托卡马克核聚变电站中的巨大高热流量,方法是将锂与等离子体一起强烈蒸发并进入等离子体进行冷却,同时使用封闭的分流器结构来限制锂的迁移。为了测试这一概念,首次设计了一个蒸气箱模块(VBM),与能够在分流器相关条件下产生等离子体的 Magnum-PSI 线性等离子体装置一起使用。其目标是将 3 千瓦目标上等离子体束的总热负荷降低 50%,并重新捕获锂,以最大限度地减少迁移和保护诊断设备。VBM 由一个带有锂储存器的加热中央箱和两个用于促进再凝结的冷侧箱组成。使用直接模拟蒙特卡洛代码 SPARTA 进行的模拟确定了 800-1000 K 的最佳工作温度,并强调了喷嘴直径和边箱长度在控制锂迁移方面的重要性。热建模显示,2 千瓦的传导加热器可以有效地达到所需的温度。基于这些发现,我们开发了 VBM 的工程设计,以评估 Magnum-PSI 中的概念,推动蒸气箱分流器走向实用化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI
The vapour box divertor concept aims to handle the tremendous high heat flux in a tokamak fusion power plant by strongly evaporating lithium with and into the plasma for cooling and using a closed divertor structure to limit lithium migration. To test this concept, a vapour box module (VBM) was designed for the first time for use with the Magnum-PSI linear plasma device, which is capable of producing plasma with divertor-relevant conditions. The goal was to reduce the total heat load from the plasma beam on the target of 3 kW by 50% and recapture lithium to minimize migration and protect diagnostics. The VBM consists of a heated central box with a lithium reservoir and two cold side boxes to promote recondensation. Simulations made with the direct simulation Monte Carlo code SPARTA determined optimal operating temperatures of 800–1000 K and highlighted the importance of the nozzle diameter and side box length in controlling lithium migration. Thermal modelling showed that a 2 kW conduction heater would efficiently reach the desired temperature. Based on these findings, an engineering design for the VBM was developed to evaluate the concept in Magnum-PSI, advancing the vapour box divertor towards practical use.
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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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