Manufacturing process and tests of a lower hybrid passive active multi-junction launcher for long pulse experiments on Tore-Supra

Guilhem, D.; Bertrand, Bernard; Lipa, M.; Achard, J.; Agarici, G.; Argouarch, A.; Belo, J.; Bej, Z.; Berger‐By, G.; Bouquey, F.; Brun, C.; Chantant, M.; Corbel, E.; Delmas, E.; Delpech, L.; Doceul, L.; Faïsse, F.; Goniche, M.; Hatchressian, Jean-Claude; Hillairet, J.; Houry, M.; Joanard, J.P.; Joubert, Pierre-Yves; Lambert, R.; Lombard, G.; Lyonne, M.; Madeleine, S.; Magne, R.; Marfisi, L.; Martinez, A.; Maury, M.; Missirlian, M.; Mollard, P.; Poli, S.; Portafaix, C.; Preynas, M.; Prou, M.; Raulin, Dominique; Rousset, E.; Samaille, F.; Saille, A.; Soler, B.; Thouvenin, D.; Verger, J.M.; Volpe, D. della; Vulliez, K.; Zago, B.

doi:10.1016/j.fusengdes.2011.01.057

Cited by 17 publications

(9 citation statements)

References 13 publications

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“…The LHCD system for WEST consists of two fully actively cooled multijunction launchers, the so-called passive active multijunction (PAM) [18] and the fully active multijunction (FAM) [19], where the latter has been modified to match the toroidal curvature of the WEST plasmas. These are fed by 16 klystrons, each capable of providing 600 kW/CW on matched load, leading to a total generator power of 10 MW/CW.…”

Section: Lower Hybrid Current Drivementioning

confidence: 99%

WEST Physics Basis

et al. 2015

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56 075020) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L-H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.

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Section: Lower Hybrid Current Drivementioning

confidence: 99%

WEST Physics Basis

et al. 2015

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“…The PAM launcher [18], which is based on an ITER-relevant design, is designed for 2.7 MW CW with a N //0 = 1.7 ± 0.2. It has a periodic assembly of passive and active waveguides, separated by 4.325 mm wide septa, and is also using 16 modules composed of a TE 10 -TE 30 mode converter.…”

Section: Description Of the West Lhcd Systemmentioning

confidence: 99%

Development of long pulse RF heating and current drive for H-mode scenarios with metallic walls in WEST

2015

AIP Conference Proceedings

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Abstract. The longstanding expertise of the Tore Supra team in long pulse heating and current drive with radiofrequency (RF) systems will now be exploited in the WEST device (tungsten-W Environment in Steady-state Tokamak) [1]. WEST will allow an integrated long pulse tokamak programme for testing W-divertor components at ITER-relevant heat flux (10-20 MW/m 2 ), while treating crucial aspects for ITER-operation, such as avoidance of W-accumulation in long discharges, monitoring and control of heat fluxes on the metallic plasma facing components (PFCs) and coupling of RF waves in H-mode plasmas. Scenario modelling using the METIS-code shows that ITER-relevant heat fluxes are compatible with the sustainment of long pulse H-mode discharges, at high power (up to 15 MW / 30 s at I P = 0.8 MA) or high fluence (up to 10 MW / 1000 s at I P = 0.6 MA) [2], all based on RF heating and current drive using Ion Cyclotron Resonance Heating (ICRH) and Lower Hybrid Current Drive (LHCD). This paper gives a description of the ICRH and LHCD systems in WEST, together with the modelling of the power deposition of the RF waves in the WEST-scenarios.

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“…4). Detailed design and manufacturing are reported in Ref [35]. Note that an uncooled PAM launcher has been tested successfully at 8 GHz on FTU [36].…”

Section: Long Pulse Operation With the Iter-relevant Lhcd System In Tmentioning

confidence: 99%

Advances in Lower Hybrid Current Drive for Tokamak Long Pulse Operation: Technology and Physics

Hoang¹,

Delpech²,

Bae

et al. 2012

Plasma and Fusion Research

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The paper gives a picture of the present status and understanding of technology and physics of Lower Hybrid Current Drive for long pulse operation in tokamaks, including the development of continuous wave (CW) high power klystrons, and its evolutions towards ITER. 3.7 GH / 700 kW CW klystrons produced in series by Thales Electron Devices are now in operation on Tore Supra. First series of eight klystrons delivered more than 4 MW to sustain non-inductive plasmas during 50 s. Moreover, a prototype of 500 kW CW klystron operating at 5 GHz developed for KSTAR by Toshiba Electron Tubes and Devices, and foreseen for ITER, is able to produce RF output powers of 300 kW / 800 s and 450 kW / 20 s on matched load. The situation on wave coupling and antennas is reported, with the latest Tore Supra results of the new CW Passive-Active Multi-junction (PAM) launcher: the antenna concept foreseen for ITER. First experiments with the PAM antenna in Tore Supra have provided extremely encouraging results in terms of power handling and coupling. Relevant ITER power density of ∼25 MW/m 2 (2.7 MW of power injected into the plasma) has been maintained over ∼80 s. In addition, LH power of 2.7 MW has been coupled at a plasma-antenna distance of 10 cm.

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Manufacturing process and tests of a lower hybrid passive active multi-junction launcher for long pulse experiments on Tore-Supra

Cited by 17 publications

References 13 publications

WEST Physics Basis

WEST Physics Basis

Development of long pulse RF heating and current drive for H-mode scenarios with metallic walls in WEST

Advances in Lower Hybrid Current Drive for Tokamak Long Pulse Operation: Technology and Physics

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