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

作者：Shahab Ud‐Din Khan, Ayesha Alam, Muhammad Abdullah, Ahmad Ali, Ali A-K. Hussain, Sehrish Shakir, Shahzaib Zahid, Riaz Khan · 发表于：Fusion Engineering and Design · 年份：2024 · DOI：10.1016/j.fusengdes.2024.114704 · 被引用次数：3 · 研究领域：Fusion materials and technologies、Nuclear reactor physics and engineering、Nuclear Materials and Properties