Divertor design for the tokamak physics experiment

D. N. Hill; B. Braams; J. N. Brooks; D. N. Ruzic; M. Ulrickson; K. A. Werley; R. Campbell; Robert James Goldston; T. Kaiser; G. H. Neilson; P. Mioduszewski; M. E. Rensink; T. D. Rognlien

doi:10.1016/0022-3115(94)00568-0

Divertor design for the tokamak physics experiment

D. N. Hill, B. Braams, J. N. Brooks, D. N. Ruzic, M. Ulrickson, K. A. Werley, R. Campbell, Robert James Goldston, T. Kaiser, G. H. Neilson, P. Mioduszewski, M. E. Rensink, T. D. Rognlien

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6 Scopus citations

Abstract

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 × L-mode), high beta (up to β_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° from normal) re-entrant divertor plate (tilted to recycle ions back toward the separatrix) will be in the range of 4–6 MW/m² with 17.5 MW of auxiliary heating power. The combination of pumping and gas puffing (D₂ plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.

Original language	English (US)
Pages (from-to)	698-702
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	220-222
DOIs	https://doi.org/10.1016/0022-3115(94)00568-0
State	Published - 1995

All Science Journal Classification (ASJC) codes

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

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10.1016/0022-3115(94)00568-0

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@article{97045e34947c488188a6eb1cd2377a0d,

title = "Divertor design for the tokamak physics experiment",

abstract = "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 × L-mode), high beta (up to βN = 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° from normal) re-entrant divertor plate (tilted to recycle ions back toward the separatrix) will be in the range of 4–6 MW/m2 with 17.5 MW of auxiliary heating power. The combination of pumping and gas puffing (D2 plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.",

author = "Hill, {D. N.} and B. Braams and Brooks, {J. N.} and Ruzic, {D. N.} and M. Ulrickson and Werley, {K. A.} and R. Campbell and Goldston, {Robert James} and T. Kaiser and Neilson, {G. H.} and P. Mioduszewski and Rensink, {M. E.} and Rognlien, {T. D.}",

year = "1995",

doi = "10.1016/0022-3115(94)00568-0",

language = "English (US)",

volume = "220-222",

pages = "698--702",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

T1 - Divertor design for the tokamak physics experiment

AU - Hill, D. N.

AU - Braams, B.

AU - Brooks, J. N.

AU - Ruzic, D. N.

AU - Ulrickson, M.

AU - Werley, K. A.

AU - Campbell, R.

AU - Goldston, Robert James

AU - Kaiser, T.

AU - Neilson, G. H.

AU - Mioduszewski, P.

AU - Rensink, M. E.

AU - Rognlien, T. D.

PY - 1995

Y1 - 1995

N2 - 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 × L-mode), high beta (up to βN = 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° from normal) re-entrant divertor plate (tilted to recycle ions back toward the separatrix) will be in the range of 4–6 MW/m2 with 17.5 MW of auxiliary heating power. The combination of pumping and gas puffing (D2 plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.

AB - 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 × L-mode), high beta (up to βN = 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° from normal) re-entrant divertor plate (tilted to recycle ions back toward the separatrix) will be in the range of 4–6 MW/m2 with 17.5 MW of auxiliary heating power. The combination of pumping and gas puffing (D2 plus impurities), along with higher heating power (45 MW maximum) will allow testing of radiative divertor concepts at ITER-like power densities.

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U2 - 10.1016/0022-3115(94)00568-0

DO - 10.1016/0022-3115(94)00568-0

M3 - Article

AN - SCOPUS:0040938910

SN - 0022-3115

VL - 220-222

SP - 698

EP - 702

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Divertor design for the tokamak physics experiment

Abstract

All Science Journal Classification (ASJC) codes

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