Fusion Reactor and Fusion Reactor Materials：Concept Design of the ITER Test Blanket Modules

• 作 者: HUANGJinhua LIZaixing ZHUYukun
• 出 处: 核工业西南物理研究院年报：英文版
• 发表日期: 2003年1期
• 关键词: 聚变堆材料 ITER 试验包层模件 概念设计 热负荷限制

Performances required: prospect to be adopted in DEMO. Shielding for V.V. and TFC in ITER. Design principles: the peak temperature and stress should not exceed technical limits. The structure of test blanket modules (TBM) should be simple for easy fabrica