Development of tungsten divertor components for ITER in Japan

FUSION ENGINEERING AND DESIGN(2018)

引用 11|浏览39
暂无评分
摘要
The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W monoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m(2) and they met the requirements for W technologies qualification programed by the IO. Upon the successful results, JADA has launched series of qualification programs toward the mass production of components. Furthermore, JADA successfully verified the water flow design inside the OVT is fulfilling the ITER requirements. The flow test was done using a OVT prototype with dummy cooling tubes.
更多
查看译文
关键词
Plasma-facing components,High heat flux,ITER,Divertor,Tungsten,Water flow
AI 理解论文
溯源树
样例
生成溯源树,研究论文发展脉络
Chat Paper
正在生成论文摘要