巴基斯坦球形托卡马克（PST）升级版平型石墨分流器模型的热液压和材料分析

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

Fusion Engineering and Design Pub Date : 2024-11-01 DOI:10.1016/j.fusengdes.2024.114704

Shahab Ud-Din Khan , Ayesha Alam , Muhammad Abdullah , Ahmad Ali , Ali Hussain , Sehrish Shakir , Shahzaib Zahid , Riaz Khan

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引用次数: 0

摘要

分流器的设计在很大程度上取决于对功率沉积、侵蚀效应和等离子体配置的管理。为巴基斯坦球形托卡马克（PST）开发的升级版双空分流器配置，采用主动冷却的石墨靶，可在 0.1 兆帕压力下承受 0.3 兆瓦/平方米的峰值热通量。本文对升级后的扁平型转发器模型系统进行了全面的热-水力和材料分析，包括材料表面热负荷、模型上的峰值温升（ΔT °C）和冷却通道中的表面温升等方面。分析包括内垂直靶（IVT）、外垂直靶（OVT）和穹顶结构的总变形（毫米）和等效应变，以及材料比较。在基于压力的瞬态分析中使用了推荐的 SST K-ω 湍流模型，入口速度为 1.5 m s-1，入口温度为 16.8 °C。使用 CFD 和 RELAP5 对材料和热液压分析进行了比较研究。研究结果表明，石墨比钨更适合用于 PST 的升级分流器系统，这表明石墨是解决 PST 热增强难题的首选表面材料。

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Thermal hydraulic and material analysis of upgraded flat-type Graphite divertor mock-up for Pakistan Spherical Tokamak (PST)

The design of a divertor is critically dependent on managing power deposition, erosion effects, and plasma configuration. An upgraded double-null divertor configuration has been developed for the Pakistan Spherical Tokamak (PST), featuring graphite targets that are actively cooled and designed to withstand a peak heat flux of 0.3 MW/m² at a pressure of 0.1 MPa. This paper presents a comprehensive thermal-hydraulic and material analysis for the upgraded flat-type divertor mock-up system, covering aspects such as material surface heat load, peak temperature rise (∆T °C) on the mock-up, and surface temperature increase in the cooling channel. The analysis includes total deformation (mm) and equivalent strain for the inner vertical target (IVT), outer vertical target (OVT), and dome structure, along with material comparison. The recommended SST K-ω turbulence model is utilized in the pressure-based transient analysis, with an inlet velocity of 1.5 m s^-1 and an inlet temperature of 16.8 °C. A comparative study of the material and thermal-hydraulic analyses was performed using CFD and RELAP5. The findings reveal that graphite is more suitable than tungsten for the PST's upgraded divertor system, demonstrating its effectiveness as the preferred surface material to address heat enhancement challenges in the PST.

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来源期刊

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.