Conceptual Design of Tungsten Monoblock Components for KSTAR Divertor

被引：0

作者：

Song, J. H. ^{[1
]}

Kim, K. M. ^{[1
]}

Im, K. ^{[1
]}

Hong, S. H. ^{[1
]}

Kim, H. T. ^{[1
]}

Kim, H. K. ^{[1
]}

Park, S. H. ^{[1
]}

Kim, B. C. ^{[1
]}

Yang, H. L. ^{[1
]}

Kim, Y. S. ^{[1
]}

机构：

[1] Natl Fus Res Inst, Adv Engn Div, Daejeon, South Korea

来源：

2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE) | 2015年

关键词：

KSTAR divertor; Tungsten monoblock; Design parameter; Fatigue lifetime; CRITICAL HEAT-FLUX;

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：

For KSTAR divertor, tungsten (W) monoblock has been considered as plasma facing components. W monoblock components consist of three parts; pure W as the plasma facing material, oxygen-free high conductive copper (Cu-OFHC) as the interlayer and CuCrZr alloy as the tube. Finite element analysis (FEA) is performed by using ANSYS WORKBENCH. In this paper, the hydraulic thermo-mechanical analysis is performed to investigate the optimal design parameters and the expected fatigue lifetime under the operating conditions in KSTAR. The design parameters, such as W armour thickness, monoblock side thickness and Cu-OFHC interlayer thickness, were found out by performing the steady state thermo-hydraulic analysis and thermo-mechanical analysis. And then, the equivalent total strains calculated by the mechanical analysis were applied to the experimental fatigue curves for CuCrZr-IG using the optimized W monoblock shape.

引用

页数：4

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