Divertor regimes in NSTX

被引：24

作者：

Soukhanovskii, VA ^{[1
]}

Maingi, R

Roquemore, AL

Boedo, J

Bush, C

Kaita, R

Kugel, HW

LeBlanc, BP

Paul, SF

Porter, GD

Wolf, NS

机构：

[1] Lawrence Livermore Natl Lab, Livermore, CA USA

[2] Oak Ridge Natl Lab, Oak Ridge, TN USA

[3] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[4] Univ Calif San Diego, La Jolla, CA 92093 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2005年 / 337卷 / 1-3期

关键词：

divertor plasma; divertor modeling; NSTX; recycling; UEDGE;

D O I：

10.1016/j.jnucmat.2004.10.135

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The identification of divertor operating regimes is of particular importance for heat and particle control optimization in high performance plasmas of a spherical torus, because of the magnetic geometry effects and compactness of the divertor region. Recent measurements of radiated power, heat, and particle fluxes in lower single null and double null NSTX plasmas with 0.8-6 MW NBI heating suggest that the inner divertor is detached at (n) over bar (e) <=, 2-3 x 10(19) m(-3) whereas the outer divertor is always attached. This resilient state exists in most L- and H-mode plasmas. The inner divertor transiently re-attaches in ELMy H-mode plasmas when heat pulses from type I or type III ELMs reach the divertor. (c) 2004 Elsevier B.V. All rights reserved.

引用

页码：475 / 479

页数：5

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