Liquid lithium wall experiments in CDX-U

被引：1

作者：

Kaita, R ^{[1
]}

Majeski, R ^{[1
]}

Luckhardt, S ^{[1
]}

Doerner, R ^{[1
]}

Finkenthal, M ^{[1
]}

Ji, H ^{[1
]}

Kugel, H ^{[1
]}

Mansfield, D ^{[1
]}

Stutman, D ^{[1
]}

Woolley, R ^{[1
]}

Zakharov, L ^{[1
]}

Zweben, S ^{[1
]}

机构：

[1] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

来源：

18TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING | 1999年

关键词：

D O I：

10.1109/FUSION.1999.849805

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

The concept of a flowing lithium first wall for a fusion reactor may lead to a significant advance in reactor design, since it could virtually eliminate the concerns with power density and erosion, tritium retention, and cooling associated with solid walls. Sputtering and erosion tests are currently underway in the PISCES device at the University of California at San Diego (UCSD). To complement this effort, plasma interaction questions in a toroidal plasma geometry will be addressed by a proposed new ground breaking experiment in the Current Drive experiment Upgrade (CDX-U) spherical torus (ST). The CDX-U plasma is intensely heated and well diagnosed, and an extensive liquid lithium plasma-facing surface will be used for the first time with a toroidal plasma. Since CDX-U is a small ST, only approximate to 1' liter or less of lithium is required to produce a toroidal liquid lithium limiter target, leading to a quick and cost-effective experiment.

引用

页码：127 / 130

页数：4

共 12 条

[1] Experimental and calculated basis of the lithium capillary system as divertor material [J].

Antonov, NV ;

Belan, VG ;

Evtihin, VA ;

Golubchikov, LG ;

Khripunov, VI ;

Korjavin, VM ;

Lyublinski, IE ;

Maynashev, VS ;

Petrov, VB ;

Pistunovich, VI ;

Pozharov, VA ;

Podkovirnov, VI ;

Shapkin, VV ;

Vertkov, AV .

JOURNAL OF NUCLEAR MATERIALS, 1997, 241 :1190-1196

[2] A NEW PLASMA-SURFACE INTERACTIONS RESEARCH FACILITY - PISCES-B AND 1ST MATERIALS EROSION EXPERIMENTS ON BULK-BORONIZED GRAPHITE [J].

HIROOKA, Y ;

CONN, RW ;

SKETCHLEY, T ;

LEUNG, WK ;

CHEVALIER, G ;

DOERNER, R ;

ELVERUM, J ;

GOEBEL, DM ;

GUNNER, G ;

KHANDAGLE, M ;

LABOMBARD, B ;

LEHMER, R ;

LUONG, P ;

RA, Y ;

SCHMITZ, L ;

TYNAN, G .

JOURNAL OF VACUUM SCIENCE & TECHNOLOGY A-VACUUM SURFACES AND FILMS, 1990, 8 (03) :1790-1797

[3]

KAITA R, 1998, P 17 IAEA FUS EN C Y

[4] Low velocity boron micro-pellet injector for edge and core impurity transport measurements [J].

Kugel, HW ;

Gorman, J ;

Kaita, R ;

Munsat, T ;

Stutman, D .

REVIEW OF SCIENTIFIC INSTRUMENTS, 1999, 70 (01) :493-497

[5]

Kugel HW, 1998, 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, P869, DOI 10.1109/FUSION.1997.687762

[6]

Labik G, 1998, 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, P873, DOI 10.1109/FUSION.1997.687763

[7]

LAZAREV V, 1999, 26 EPS C CONTR FUS P

[8] MEASUREMENT OF THE LOCAL PARTICLE DIFFUSION-COEFFICIENT IN A MAGNETIZED PLASMA [J].

LEVINTON, FM ;

MEYERHOFER, DD .

REVIEW OF SCIENTIFIC INSTRUMENTS, 1987, 58 (08) :1393-1400

[9] Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning [J].

Mansfield, DK ;

Hill, KW ;

Strachan, JD ;

Bell, MG ;

Scott, SD ;

Budny, R ;

Marmar, ES ;

Snipes, JA ;

Terry, JL ;

Batha, S ;

Bell, RE ;

Bitter, M ;

Bush, CE ;

Chang, Z ;

Darrow, DS ;

Ernst, D ;

Fredrickson, E ;

Grek, B ;

Herrmann, HW ;

Janos, A ;

Jassby, DL ;

Jobes, FC ;

Johnson, DW ;

Johnson, LC ;

Levinton, FM ;

Mikkelsen, DR ;

Mueller, D ;

Owens, DK ;

Park, H ;

Ramsey, AT ;

Roquemore, AL ;

Skinner, CH ;

Stevenson, T ;

Stratton, BC ;

Synakowski, E ;

Taylor, G ;

vonHalle, A ;

vonGoeler, S ;

Wong, KL ;

Zweben, SJ .

PHYSICS OF PLASMAS, 1996, 3 (05) :1892-1897

[10] High-harmonic fast magnetosonic wave coupling, propagation, and heating in a spherical torus plasma [J].

Menard, J ;

Majeski, R ;

Kaita, R ;

Ono, M ;

Munsat, T ;

Stutman, D ;

Finkenthal, M .

PHYSICS OF PLASMAS, 1999, 6 (05) :2002-2008

← 1 2 →