ARIES-ST plasma-facing component design and analysis

被引:3
作者
Tillack, MS [1 ]
Wang, XR
Pulsifer, J
Sviatoslavsky, I
机构
[1] Univ Calif San Diego, Fus Energy Res Program, La Jolla, CA 92093 USA
[2] Univ Wisconsin, Fus Technol Inst, Madison, WI 53706 USA
关键词
plasma-facing components; spherical plasma; power;
D O I
10.1016/S0920-3796(00)00397-5
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
ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio 'spherical torus' (ST) plasma. The plasma-facing components include the inboard and outboard first wall, divertor plates, and plasma stability plates. Several unique aspects of ST plasma influence the engineering design. The limited inboard space precludes a full inboard divertor slot, such that substantial power and particle flows are expected to impact the inboard first wall. Strong requirements on plasma vertical stability require close-in conductors. The use of He-cooled tungsten for the stability plates allows them to act as plasma-interactive components operating at high temperature and moderately high (1-2 MW/m(2)) heat flux. High plasma core radiation fraction and a natural tendency for low inboard transport losses help to alleviate these inboard problems, such that the peak power loads are not expected to exceed the capability of He-cooled tungsten and steel structures. The main features of the plasma-facing components are summarized here together with the analysis of their thermal hydraulic and thermomechanical performance. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:363 / 369
页数:7
相关论文
共 8 条
[1]  
CAMPBELL GO, 1995, SAE AER ATL C DAYT O
[2]   Assessment of tungsten for use in the ITER plasma facing components [J].
Davis, JW ;
Barabash, VR ;
Makhankov, A ;
Plochl, L ;
Slattery, KT .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :308-312
[3]   NORMAL FLOW HEAT-EXCHANGER FOR DIVERTOR PANEL COOLING [J].
IZENSON, MG ;
VALENZUELA, JA .
FUSION TECHNOLOGY, 1992, 21 (03) :1828-1834
[4]  
ROSENFELD J. H., 1996, P INT C POR MED THEI
[5]  
Sherman A. J., 1990, P 1990 MRS FALL M BO
[6]  
TILLACK MS, IN PRESS CONFIGURATI
[7]   Externally-driven H-mode studies in CCT [J].
Tynan, GR ;
Liberati, J ;
Pribyl, P ;
Taylor, RJ ;
Wells, B .
PLASMA PHYSICS AND CONTROLLED FUSION, 1996, 38 (08) :1301-1305
[8]   ARIES-RS divertor system selection and analysis [J].
Wong, CPC ;
Chin, E ;
Petrie, TW ;
Reis, EE ;
Tillack, M ;
Wang, X ;
Sviatoslavsky, I ;
Malang, S ;
Sze, DK .
FUSION ENGINEERING AND DESIGN, 1997, 38 (1-2) :115-137