DIVERTOR DESIGN FOR THE TOKAMAK PHYSICS EXPERIMENT

被引：6

作者：

HILL, DN

BRAAMS, B

BROOKS, JN

RUZIC, DN

ULRICKSON, M

WERLEY, KA

CAMPBELL, R

GOLDSTON, R

KAISER, T

NEILSON, GH

MIODUSZEWSKI, P

RENSINK, ME

ROGNLIEN, TD

机构：

[1] NYU, COURANT INST MATH SCI, NEW YORK, NY 10012 USA

[2] ARGONNE NATL LAB, ARGONNE, IL 60439 USA

[3] UNIV ILLINOIS, URBANA, IL 61801 USA

[4] SANDIA NATL LABS, ALBUQUERQUE, NM 87185 USA

[5] LOS ALAMOS NATL LAB, LOS ALAMOS, NM 87545 USA

[6] PRINCETON PLASMA PHYS LAB, PRINCETON, NJ 08543 USA

[7] OAK RIDGE NATL LAB, OAK RIDGE, TN 37831 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1995年 / 220卷

关键词：

D O I：

10.1016/0022-3115(94)00568-0

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

In this paper we discuss the divertor design for the planned TPX tokamak, which will explore the physics and technology of steady state (1000 s pulses) heat and particle removal in high confinement (up to 4 x L-mode), high beta (up to beta(N) = 5) divertor plasmas sustained by non-inductive current drive. TPX will operate in the double-null divertor configuration, with actively cooled graphite targets forming a deep (0.57 m) slot at the outer strike point. The peak heat flux on the highly tilted (74 degrees from normal) re-entrant divertor plate (tilted to recycle ions back toward the separatrix) will be in the range of 4-6 MW/m(2) with 17.5 MW of auxiliary heating power. The combination of pumping and gas puffing (D-2 plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.

引用

页码：698 / 702

页数：5