Microwave stray radiation: Measures for steady state diagnostics at Wendelstein 7-X

Hathiramani, D.; Binder, Roland; Brakel, R.; Broszat, T.; Brucker, B.; Cardella, A.; Endler, M.; Grosser, K.; Hirsch, M.; Laqua, H. P.; Thiel, Stefan

doi:10.1016/j.fusengdes.2013.01.003

Cited by 19 publications

(15 citation statements)

References 8 publications

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“…While good results are obtained with the power balance at the MISTRAL test facility in Greifswald [6,7], care should be taken when applied to ITER. The interior of the MISTRAL is simple and has been optimized for isotropic stray radiation.…”

Section: Stray Radiation Power Density Ecwmentioning

confidence: 99%

Loads due to stray microwave radiation in ITER

Oosterbeek

Udintsev

Gandini

et al. 2015

Fusion Engineering and Design

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a b s t r a c tHigh-power microwaves generated by gyrotrons will be extensively used in ITER for a variety of purposes such as assisting plasma breakdown, plasma heating, current drive, tearing mode suppression and as a probing beam for the Collective Thomson Scattering diagnostic. In a number of these schemes absorption of the microwaves by the plasma will not be full and in some cases there could be no absorption at all. This may result in a directed beam with a high microwave power flux or -depending on location and plasma conditions -an approximately isotropic microwave power field. The contribution of electron cyclotron emission to these power densities is briefly discussed. Exposure to in-vessel components leads to absorption by metals and ceramics. In this paper microwave power densities are estimated and, following a brief review of absorption, thermal loads on in-vessel components are assessed. The paper is concluded by a discussion of the current approach to control such loads.

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Section: Stray Radiation Power Density Ecwmentioning

confidence: 99%

Loads due to stray microwave radiation in ITER

Oosterbeek

Udintsev

Gandini

et al. 2015

Fusion Engineering and Design

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“…It has to be considered that the experimental campaign in W7-X will be characterized by ECRH heating system with a power of 7M W at the frequency f ECRH = 140GHz. The discharge lengths will eventually approach 10-20 s. In these conditions the definition of the ECRH stray radiation is P ECRH−stray = 50kW/m 2 [18].…”

Section: Design Of a Shield For The Magnetic Sensorsmentioning

confidence: 99%

“…The magnetic pick-up coil sensors constitute an important part of the HRP head design and a specific attention is devoted to this issue. It could be considered that the probe head will be installed on the MPM and most of the time the probe head will be located on the "park position", behind the first wall elements, where a reduction of 25% on the radiation power can be expected and a further reduction due to the relative distance of ECRH launchers [18].…”

Section: Design Of a Shield For The Magnetic Sensorsmentioning

confidence: 99%

Design of a High Resolution Probe Head for Electromagnetic Turbulence Investigations in W7-X

Agostinetti¹,

Spolaore²,

Brombin³

et al. 2018

IEEE Trans. Plasma Sci.

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An insertable probe head called High Resolution Probe (HRP) has been developed at Consorzio RFX in the framework of the EUROfusion S1 work program and in collaboration with IPP Greifswald, to study the electrostatic and electromagnetic features of turbulence in the edge region of Wendelstein 7-X using the Multi-Purpose Manipulator (MPM). The paper reports the design development of the HRP diagnostic head, from the choice of the sensors to the engineering design. The assumptions and evaluations supporting the main design choices, together with the R&D tests carried out to check the most critical parts, are described in detail.Index Terms-insertable probe, electromagnetic fluctuations, stellarator, W7-X

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“…For example, a higher thermal conductivity usually goes along with a higher electric conductivity which could be in conflict with an increased electromagnetic force during plasma decay. Any shielding against ECRH stray radiation may cause trapped volumes, which have to be avoided with respect to the vacuum compatibility [15]. A design has to fit into a tight available space with limited access, but on the other hand attachment screws have to be large enough to be handled with gloves or have to be protected against losses during installation.…”

Section: General Design Remarksmentioning

confidence: 99%

Upgrades of edge, divertor and scrape-off layer diagnostics of W7‐X for OP1.2

Hathiramani

Ali

Anda

et al. 2018

Fusion Engineering and Design

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Wendelstein 7-X (W7-X) is the world's largest superconducting nuclear fusion experiment of the optimized stellarator type. In the first Operation Phase (OP1.1) helium and hydrogen plasmas were studied in limiter configuration. The heating energy was limited to 4 MJ and the main purpose of that campaign was the integral commissioning of the machine and diagnostics, which was achieved very successfully. Already from the beginning a comprehensive set of diagnostics was available to study the plasma. On the path towards high-power, high-performance plasmas, W7-X will be stepwise upgraded from an inertially cooled (OP1.2, limited to 80 MJ) to an actively cooled island divertor (OP2, 10 MW steady-state plasma operation). The machine is prepared for OP1.2 with 10 inertially cooled divertor units, and the experimental campaign has started recently.The paper describes a subset of diagnostics which will be available for OP1.2 to study the plasma edge, divertor and scrape-off layer physics including those already available for OP1.1, plus modifications, upgrades and new systems. The focus of this summary will be on technical and engineering aspects, like feasibility and assembly but also on reliability, thermal loads and shielding against magnetic fields.

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Microwave stray radiation: Measures for steady state diagnostics at Wendelstein 7-X

Cited by 19 publications

References 8 publications

Loads due to stray microwave radiation in ITER

Loads due to stray microwave radiation in ITER

Design of a High Resolution Probe Head for Electromagnetic Turbulence Investigations in W7-X

Upgrades of edge, divertor and scrape-off layer diagnostics of W7‐X for OP1.2

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