Divertor regimes in NSTX

V. A. Soukhanovskii; R. Maingi; A. L. Roquemore; J. Boedo; C. Bush; R. Kaita; H. W. Kugel; B. P. Leblanc; S. F. Paul; G. D. Porter; N. S. Wolf

doi:10.1016/j.jnucmat.2004.10.135

Divertor regimes in NSTX

V. A. Soukhanovskii
, R. Maingi
, A. L. Roquemore
, J. Boedo
, C. Bush
, R. Kaita
, H. W. Kugel
, B. P. Leblanc
, S. F. Paul
, G. D. Porter
, N. S. Wolf

PPPL NSTX

Research output: Contribution to journal › Article › peer-review

32 Scopus citations

Abstract

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 n̄e≤2-3×1019m-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.

Original language	English (US)
Pages (from-to)	475-479
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	337-339
Issue number	1-3 SPEC. ISS.
DOIs	https://doi.org/10.1016/j.jnucmat.2004.10.135
State	Published - Mar 1 2005

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Keywords

Divertor modeling
Divertor plasma
NSTX
Recycling
UEDGE

Access to Document

10.1016/j.jnucmat.2004.10.135

Cite this

@article{616c243b994a4ebf88110c090c454ef3,

title = "Divertor regimes in NSTX",

abstract = "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}e≤2-3×1019m-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.",

keywords = "Divertor modeling, Divertor plasma, NSTX, Recycling, UEDGE",

author = "Soukhanovskii, \{V. A.\} and R. Maingi and Roquemore, \{A. L.\} and J. Boedo and C. Bush and R. Kaita and Kugel, \{H. W.\} and Leblanc, \{B. P.\} and Paul, \{S. F.\} and Porter, \{G. D.\} and Wolf, \{N. S.\}",

year = "2005",

month = mar,

day = "1",

doi = "10.1016/j.jnucmat.2004.10.135",

language = "English (US)",

volume = "337-339",

pages = "475--479",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "1-3 SPEC. ISS.",

}

TY - JOUR

T1 - Divertor regimes in NSTX

AU - Soukhanovskii, V. A.

AU - Maingi, R.

AU - Roquemore, A. L.

AU - Boedo, J.

AU - Bush, C.

AU - Kaita, R.

AU - Kugel, H. W.

AU - Leblanc, B. P.

AU - Paul, S. F.

AU - Porter, G. D.

AU - Wolf, N. S.

PY - 2005/3/1

Y1 - 2005/3/1

N2 - 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 n̄e≤2-3×1019m-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.

AB - 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 n̄e≤2-3×1019m-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.

KW - Divertor modeling

KW - Divertor plasma

KW - NSTX

KW - Recycling

KW - UEDGE

UR - https://www.scopus.com/pages/publications/13844314604

UR - https://www.scopus.com/pages/publications/13844314604#tab=citedBy

U2 - 10.1016/j.jnucmat.2004.10.135

DO - 10.1016/j.jnucmat.2004.10.135

M3 - Article

AN - SCOPUS:13844314604

SN - 0022-3115

VL - 337-339

SP - 475

EP - 479

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 SPEC. ISS.

ER -

Divertor regimes in NSTX

Abstract

All Science Journal Classification (ASJC) codes

Keywords

Access to Document

Other files and links

Fingerprint

Cite this