Improved Geometrical Design of the US DCLL ITER Test Blanket Module

被引：0

作者：

Marriott, E. ^{[1
]}

Sawan, M. ^{[1
]}

Dagher, M. ^{[2
]}

Wong, C. ^{[3
]}

机构：

[1] Univ Wisconsin, Fus Technol Inst, Madison, WI 53706 USA

[2] Univ Calif Los Angeles, Los Angeles, CA 90095 USA

[3] Gen Atom, San Diego, CA 92121 USA

来源：

2011 IEEE/NPSS 24TH SYMPOSIUM ON FUSION ENGINEERING (SOFE) | 2011年

关键词：

ITER; blanket; test blanket module; CFD;

D O I：

暂无

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Computational fluid dynamics simulations have demonstrated flow problems within the helium flow path in the current US DCLL ITER test blanket module design. New geometry for the helium flow path has been designed that will improve flow evenness and simplify the overall helium flow path within the test blanket module while maintaining the overall test blanket module geometry. Global changes to the test blanket module geometry can be implemented based on these improvements.

引用

页数：6