THE DESIGN OF THE TOKAMAK PHYSICS EXPERIMENT (TPX)

被引：11

作者：

SCHMIDT, JA

THOMASSEN, KI

GOLDSTON, RJ

NEILSON, GH

NEVINS, WM

SINNIS, JC

ANDERSON, P

BAIR, W

BARR, WL

BATCHELOR, DB

BAXI, C

BERG, G

BERNABEI, S

BIALEK, JM

BONOLI, PT

BOOZER, A

BOWERS, D

BRONNER, G

BROOKS, JN

BROWN, TG

BULMER, R

BUTNER, D

CAMPBELL, R

CASPER, T

CHANIOTAKIS, E

CHAPLIN, M

CHEN, SJ

CHIN, E

CHRZANOWSKI, J

CITROLO, J

COLE, MJ

DAHLGREN, F

DAVIS, FC

DAVIS, J

DAVIS, S

DIATCHENKO, N

DINKEVICH, S

FELDSHTEYN, Y

FELKER, B

FENG, T

FENSTERMACHER, ME

FLEMING, R

FOGARTY, PJ

FRAGETTA, W

FREDD, E

GABLER, M

GALAMBOS, J

GOHAR, Y

GORANSON, PL

GREENOUGH, N

机构：

[1] Princeton Plasma Physics Lab, Princeton, New Jersey

[2] Lawrence Livermore National Lab, Livermore, California

[3] Oak Ridge National Lab, Oak Ridge, Tennessee

[4] General Atomics, San Diego, California

[5] Ebasco Services, New York

[6] Rockwell International, Canoga Park, California

[7] Massachusetts Institute of Technology, Cambridge, Massachusetts

[8] College of William and Mary, Williamsburg, Virginia

[9] McDonnell Douglas Missile Systems, St. Louis, Missouri

[10] Argonne National Lab, Argonne, Illinois

[11] Grumman Space and Electronic Div., Princeton, New Jersey

[12] Sandia National Lab, Albuquerque, New Mexico

[13] University of Illinois at Urbana-Champaign, Urbana, Illinois

[14] University of California at Los Angeles, Los Angeles, California

[15] Los Alamos National Lab, Los Alamos, New Mexico

[16] University of Wisconsin, Madison, Wisconsin

[17] Idaho National Engineering Lab, Idaho Falls, Idaho

[18] Columbia University, New York

来源：

JOURNAL OF FUSION ENERGY | 1993年 / 12卷 / 03期

关键词：

D O I：

10.1007/BF01079667

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：

The Tokamak Physics Experiment is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. It is based on an emerging class of tokamak operating modes, characterized by beta limits well in excess of the Troyon limit, confinement scaling well in excess of H-mode, and bootstrap current fractions approaching unity. Such modes are attainable through the use of advanced, steady state plasma controls including strong shaping, current profile control, and active particle recycling control. Key design features of the TPX are superconducting toroidal and poloidal fields coils; actively-cooled plasma-facing components; a flexible heating and current drive system; and a spacious divertor for flexibility. Substantial deuterium plasma operation is made possible with an in-vessel remote maintenance system, a low-activation titanium vacuum vessel, and shielding of ex-vessel components. The facility will be constructed as a national project with substantial participation by U.S. industry. Operation will begin with first plasma in the year 2000.

引用

页码：221 / 258

页数：38

共 4 条

[1]

Texter S., Et al., Phys. Lett. A, 175, (1993)

[2]

Kikuchi M., Nucl. Fusion, 30, (1990)

[3]

Uckan N.A., Et al., ITER Physics Design Guidelines: 1989, (1990)

[4]

Petrie T., Et al., Divertor heat flux reduction by D<sub>2</sub> injection in DIII-D, Bull. Am. Phys. Soc., 37, (1992)

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