Heat flux scaling experiments in NSTX

R. Maingi; H. W. Kugel; C. J. Lasnier; A. L. Roquemore; V. A. Soukhanovskii; C. E. Bush

doi:10.1016/S0022-3115(02)01441-1

Heat flux scaling experiments in NSTX

R. Maingi
, H. W. Kugel
, C. J. Lasnier
, A. L. Roquemore
, V. A. Soukhanovskii
, C. E. Bush

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

8 Scopus citations

Abstract

We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ˜6 MW/m² at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target.

Original language	English (US)
Pages (from-to)	1005-1009
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	313
Issue number	316
DOIs	https://doi.org/10.1016/S0022-3115(02)01441-1
State	Published - Mar 2003
Externally published	Yes

All Science Journal Classification (ASJC) codes

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

Keywords

Boundary plasmas
Divertor
Heat flux
Infrared thermogrpahy
Plasma-wall interactions
Power balance

Access to Document

10.1016/S0022-3115(02)01441-1

Cite this

@article{e83d0ec24014417bb4c8898c56d9bf8a,

title = "Heat flux scaling experiments in NSTX",

abstract = "We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ˜6 MW/m2 at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30\% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target.",

keywords = "Boundary plasmas, Divertor, Heat flux, Infrared thermogrpahy, Plasma-wall interactions, Power balance",

author = "R. Maingi and Kugel, \{H. W.\} and Lasnier, \{C. J.\} and Roquemore, \{A. L.\} and Soukhanovskii, \{V. A.\} and Bush, \{C. E.\}",

year = "2003",

month = mar,

doi = "10.1016/S0022-3115(02)01441-1",

language = "English (US)",

volume = "313",

pages = "1005--1009",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "316",

}

TY - JOUR

T1 - Heat flux scaling experiments in NSTX

AU - Maingi, R.

AU - Kugel, H. W.

AU - Lasnier, C. J.

AU - Roquemore, A. L.

AU - Soukhanovskii, V. A.

AU - Bush, C. E.

PY - 2003/3

Y1 - 2003/3

N2 - We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ˜6 MW/m2 at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target.

AB - We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ˜6 MW/m2 at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target.

KW - Boundary plasmas

KW - Divertor

KW - Heat flux

KW - Infrared thermogrpahy

KW - Plasma-wall interactions

KW - Power balance

UR - https://www.scopus.com/pages/publications/17444439572

UR - https://www.scopus.com/pages/publications/17444439572#tab=citedBy

U2 - 10.1016/S0022-3115(02)01441-1

DO - 10.1016/S0022-3115(02)01441-1

M3 - Article

AN - SCOPUS:17444439572

SN - 0022-3115

VL - 313

SP - 1005

EP - 1009

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 316

ER -

Heat flux scaling experiments in NSTX

Abstract

All Science Journal Classification (ASJC) codes

Keywords

Access to Document

Other files and links

Fingerprint

Cite this