CDX-U operation with a large area liquid lithium limiter

R. Majeski; M. Boaz; D. Hoffman; B. Jones; R. Kaita; H. Kugel; T. Munsat; J. Spaleta; V. Soukhanovskii; J. Timberlake; L. Zakharov; G. Antar; R. Doerner; S. Luckhardt; R. W. Conn; M. Finkenthal; D. Stutman; R. Maingi; M. Ulrickson

doi:10.1016/S0022-3115(02)01365-X

CDX-U operation with a large area liquid lithium limiter

R. Majeski, M. Boaz, D. Hoffman, B. Jones, R. Kaita, H. Kugel, T. Munsat, J. Spaleta, V. Soukhanovskii, J. Timberlake, L. Zakharov, G. Antar, R. Doerner, S. Luckhardt, R. W. Conn, M. Finkenthal, D. Stutman, R. Maingi, M. Ulrickson

PPPL Tokamak Expermntl Science

Research output: Contribution to journal › Conference article › peer-review

32 Scopus citations

Abstract

The current drive experiment-upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact (R=34 cm, a=22 cm, B_toroidal=2 kG, I_P=100 kA, T_e(0)~100 eV, n_e(0)~5×10¹⁹ m^-3) short-pulse (<25 ms) spherical torus with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. Surface coatings are evident on part of the lithium. Despite the surface coatings, tokamak discharges operated in contact with the lithium-filled tray show evidence of reduced impurities and recycling. The reduction in recycling is largest when the lithium is liquefied.

Original language	English (US)
Pages (from-to)	625-629
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	313-316
Issue number	SUPPL.
DOIs	https://doi.org/10.1016/S0022-3115(02)01365-X
State	Published - Mar 2003
Event	Plasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japan Duration: May 26 2002 → May 31 2002

All Science Journal Classification (ASJC) codes

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

Keywords

Limiter
Lithium
Tokamak

Access to Document

10.1016/S0022-3115(02)01365-X

Cite this

Majeski, R., Boaz, M., Hoffman, D., Jones, B., Kaita, R., Kugel, H., Munsat, T., Spaleta, J., Soukhanovskii, V., Timberlake, J., Zakharov, L., Antar, G., Doerner, R., Luckhardt, S., Conn, R. W., Finkenthal, M., Stutman, D., Maingi, R., & Ulrickson, M. (2003). CDX-U operation with a large area liquid lithium limiter. Journal of Nuclear Materials, 313-316(SUPPL.), 625-629. https://doi.org/10.1016/S0022-3115(02)01365-X

@article{a9da97878df84e899503b6867dbc5428,

title = "CDX-U operation with a large area liquid lithium limiter",

abstract = "The current drive experiment-upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact (R=34 cm, a=22 cm, Btoroidal=2 kG, IP=100 kA, Te(0)\textasciitilde{}100 eV, ne(0)\textasciitilde{}5×1019 m-3) short-pulse (<25 ms) spherical torus with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. Surface coatings are evident on part of the lithium. Despite the surface coatings, tokamak discharges operated in contact with the lithium-filled tray show evidence of reduced impurities and recycling. The reduction in recycling is largest when the lithium is liquefied.",

keywords = "Limiter, Lithium, Tokamak",

author = "R. Majeski and M. Boaz and D. Hoffman and B. Jones and R. Kaita and H. Kugel and T. Munsat and J. Spaleta and V. Soukhanovskii and J. Timberlake and L. Zakharov and G. Antar and R. Doerner and S. Luckhardt and Conn, \{R. W.\} and M. Finkenthal and D. Stutman and R. Maingi and M. Ulrickson",

year = "2003",

month = mar,

doi = "10.1016/S0022-3115(02)01365-X",

language = "English (US)",

volume = "313-316",

pages = "625--629",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "SUPPL.",

note = "Plasma - Surface Interactions in Controlled Fusion Devices ; Conference date: 26-05-2002 Through 31-05-2002",

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Majeski, R, Boaz, M, Hoffman, D, Jones, B, Kaita, R, Kugel, H, Munsat, T, Spaleta, J, Soukhanovskii, V, Timberlake, J, Zakharov, L, Antar, G, Doerner, R, Luckhardt, S, Conn, RW, Finkenthal, M, Stutman, D, Maingi, R & Ulrickson, M 2003, 'CDX-U operation with a large area liquid lithium limiter', Journal of Nuclear Materials, vol. 313-316, no. SUPPL., pp. 625-629. https://doi.org/10.1016/S0022-3115(02)01365-X

TY - JOUR

T1 - CDX-U operation with a large area liquid lithium limiter

AU - Majeski, R.

AU - Boaz, M.

AU - Hoffman, D.

AU - Jones, B.

AU - Kaita, R.

AU - Kugel, H.

AU - Munsat, T.

AU - Spaleta, J.

AU - Soukhanovskii, V.

AU - Timberlake, J.

AU - Zakharov, L.

AU - Antar, G.

AU - Doerner, R.

AU - Luckhardt, S.

AU - Conn, R. W.

AU - Finkenthal, M.

AU - Stutman, D.

AU - Maingi, R.

AU - Ulrickson, M.

PY - 2003/3

Y1 - 2003/3

N2 - The current drive experiment-upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact (R=34 cm, a=22 cm, Btoroidal=2 kG, IP=100 kA, Te(0)~100 eV, ne(0)~5×1019 m-3) short-pulse (<25 ms) spherical torus with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. Surface coatings are evident on part of the lithium. Despite the surface coatings, tokamak discharges operated in contact with the lithium-filled tray show evidence of reduced impurities and recycling. The reduction in recycling is largest when the lithium is liquefied.

AB - The current drive experiment-upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact (R=34 cm, a=22 cm, Btoroidal=2 kG, IP=100 kA, Te(0)~100 eV, ne(0)~5×1019 m-3) short-pulse (<25 ms) spherical torus with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. Surface coatings are evident on part of the lithium. Despite the surface coatings, tokamak discharges operated in contact with the lithium-filled tray show evidence of reduced impurities and recycling. The reduction in recycling is largest when the lithium is liquefied.

KW - Limiter

KW - Lithium

KW - Tokamak

UR - https://www.scopus.com/pages/publications/0037340459

UR - https://www.scopus.com/inward/citedby.url?scp=0037340459&partnerID=8YFLogxK

U2 - 10.1016/S0022-3115(02)01365-X

DO - 10.1016/S0022-3115(02)01365-X

M3 - Conference article

AN - SCOPUS:0037340459

SN - 0022-3115

VL - 313-316

SP - 625

EP - 629

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL.

T2 - Plasma - Surface Interactions in Controlled Fusion Devices

Y2 - 26 May 2002 through 31 May 2002

ER -

CDX-U operation with a large area liquid lithium limiter

Abstract

All Science Journal Classification (ASJC) codes

Keywords

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