Status of power balance monitoring for long pulse operation at Tore Supra

被引：22

作者：

Reichle, R ^{[1
]}

Guilhem, D ^{[1
]}

Mitteau, R ^{[1
]}

Vallet, JC ^{[1
]}

Balorin, C ^{[1
]}

Bibet, P ^{[1
]}

Chantant, M ^{[1
]}

Delchambre, E ^{[1
]}

Desgrange, C ^{[1
]}

Ducobu, L ^{[1
]}

Ekedahl, A ^{[1
]}

Escourbiac, F ^{[1
]}

Faisse, F ^{[1
]}

Geraud, A ^{[1
]}

Goniche, M ^{[1
]}

Jouve, M ^{[1
]}

Lipa, M ^{[1
]}

Martin, G ^{[1
]}

Messina, P ^{[1
]}

Moulin, D ^{[1
]}

Pocheau, C ^{[1
]}

Roche, H ^{[1
]}

Saille, A ^{[1
]}

Saint-Laurent, F ^{[1
]}

Schlosser, J ^{[1
]}

Thomas, E ^{[1
]}

Tsitrone, E ^{[1
]}

机构：

[1] CE Cadarache, Assic CEA Fus, DRFC, DSM, F-13108 St Paul Les Durance, France

来源：

NUCLEAR FUSION | 2003年 / 43卷 / 09期

关键词：

D O I：

10.1088/0029-5515/43/9/301

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

A short review of diagnostics and techniques for active power exhaust control is given from the point of view of experiences gained at Tore Supra. The physical and technological aspects are presented with the aim of illustrating strengths, difficulties and potential for future long pulse and steady state fusion devices such as W7X and ITER-FEAT. One of the main features of the Tore Supra approach to power exhaust control is the reliance on infrared (IR) thermography to survey nearly 100% of the high flux target zones. This is applied to the largest elements, the toroidal pump limiter and the heating antennae, by a number of IR endoscopes. For high flux target areas inaccessible to direct view, optical fibres in the IR and the near-IR range are used. The large wall panels, which evacuate the rest of the power, are controlled by calorimetry. Bolometry is used to achieve a complete power balance. These measurements can be inserted in control loops acting typically on the injected heating power or the radiation cooling.

引用

页码：797 / 804

页数：8

共 23 条

[1]

CHANTANT M, 2001, CONTR 3 IAEA TCM STE

[2]

DELCHAMBRE E, 2003, P 30 EPS CONTR FUS P, V27

[3] Infrared surface temperature measurement for long pulse real time feed-back control in an actively cooled machine [J].

Guilhem, D ;

Martin, G ;

Reichle, R ;

Roche, H ;

Jouve, M ;

Ducobu, L ;

Messina, P .

REVIEW OF SCIENTIFIC INSTRUMENTS, 1999, 70 (01) :427-430

[4] Plasma-wall interaction issues in ITER [J].

Janeschitz, G .

JOURNAL OF NUCLEAR MATERIALS, 2001, 290 :1-11

[5] Development and testing of diagnostic windows for Tore Supra/CIEL and ITER [J].

Lipa, M ;

Portafaix, C ;

Pluyette, E ;

Walker, C ;

Lochet, N .

FUSION ENGINEERING AND DESIGN, 2002, 61-62 :801-806

[6] Heat flux pattern on the toroidal pump limiter of Tore Supra:: first observations and preliminary analysis [J].

Mitteau, R ;

Vallet, JC ;

Moal, A ;

Guilhem, D ;

Schlosser, J ;

Loarer, T ;

Riou, B ;

Grosman, A ;

Géraud, A ;

Ghendrih, P ;

Tsitrone, E ;

Pegourié, B ;

Ané, JM .

JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :1229-1233

[7] The data acquisition system for the infrared cameras on Tore Supra [J].

Moulin, D ;

Balorin, C ;

Buravand, Y ;

Caulier, G ;

Ducobu, L ;

Guilhem, D ;

Jouve, A ;

Roche, H .

IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2002, 49 (02) :423-427

[8]

Reichle R, 1996, DIAGNOSTICS FOR EXPERIMENTAL THERMONUCLEAR FUSION REACTORS, P559

[9] Low energy neutral particle fluxes in the JET divertor [J].

Reichle, R ;

Ehrenberg, JK ;

Gottardi, NAC ;

Horton, LD ;

Ingesson, LC ;

Jackel, HJ ;

McCormick, GK ;

Loarte, A ;

Simonini, R ;

Stamp, MF .

JOURNAL OF NUCLEAR MATERIALS, 1997, 241 :456-461

[10] Surface temperature measurements on Tokamak target plates with two types of infra red [J].

Reichle, R ;

Pocheau, C ;

Delchambre, E ;

Ducobu, L ;

Faisse, F ;

Guilhem, D ;

Jouve, M ;

Moulin, D ;

Roche, H ;

Thomas, E .

JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :711-715

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