Experimental optimisation of a hypervapotron® concept for ITER plasma facing components

被引：44

作者：

Escourbiac, F

Schlosser, J

Merola, M

Vastra, IB

机构：

[1] CEA Cadarache, DRFC SIPP, CEA DSM DRFC, Assoc Euratom CEA,Dept Rech Fus Controlee, F-13108 St Paul Les Durance, France

[2] EFDA Close Support Unit, D-85748 Garching, Germany

[3] FRAMATOME ANP, Ctr Tech, F-71200 Le Creusot, France

来源：

FUSION ENGINEERING AND DESIGN | 2003年 / 66-68卷

关键词：

hypervapotron (R); critical heat flux;

D O I：

10.1016/S0920-3796(03)00172-8

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：

Historically developed for cooling of klystron electronic tubes, metallic hypervapotron((R)) prototypes with different width were manufactured for high heat flux plasma facing components (PFC) applications. They were critical heat flux (CHF) tested on the European 200 kW electron beam facility (FE200), the 54 measured values have shown their good performances-up to 25-30 MW/m(2) at low axial velocities (2-6 m/s)-interesting for ITER divertor dome and vertical target design. An important conclusion is that CHF decreases when the width increases. (C) 2003 Elsevier Science B.V. All rights reserved.

引用

页码：301 / 304

页数：4