Preliminary design of the ITER ECH upper launcher

Strauß, D.; Aiello, G.; Chavan, R.; Cirant, S.; deBaar, M.; Farina, D.; Gantenbein, G.; Goodman, T.; Henderson, M.; Kasparek, W.; Kleefeldt, K.; Landis, J.‐D.; Meier, Andreas; Moro, A.; Plaum, B.; Poli, E.; Ramponi, G.; Ronden, D.; Saibene, G.; Sánchez, F.; Sautter, O.; Scherer, T.; Schreck, S.; Serikov, A.; Sozzi, C.; Spaeh, P.; Vaccaro, A.; Zohm, H.

doi:10.1109/plasma.2011.5993099

Cited by 4 publications

(5 citation statements)

References 19 publications

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“…The design development is based on the preliminary design of the four upper launchers [1] and the actual intermediate design is shown in figure 2.…”

Section: Design Statusmentioning

confidence: 99%

“…The four ITER ECRH Upper Launchers (UL, see figure 1 and [1]) are plasma facing port plugs located in the ITER upper ports, their development is driven by ITER with European support by F4E. The Upper Launcher design is developed by the European ECH Upper Launcher Consortium of Associations ECHUL-CA (KIT/Germany, CNR/Italy, CRPP/Switzerland, Differ/Netherlands, IPP and IPF/Germany).…”

Section: Introductionmentioning

confidence: 99%

“…The upper launcher millimeter wave power injection system is complemented by an equatorial launcher (JAEA, [4]) for central plasma heating and off-axis current drive. This publication gives an overview of the developments towards final design since the preliminary design review of the ITER ERCH Upper Launchers [1]. The technical requirements describe criteria which should be fulfilled to obtain a working design.…”

Section: Introductionmentioning

confidence: 99%

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Progress of the ECRH Upper Launcher design for ITER

Strauß

Aiello

Bruschi

et al. 2014

Fusion Engineering and Design

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The design of the ITER ECRH system provides 20MW millimeter wave power for central plasma heating and MHD stabilization. The system consists of an array of 24 gyrotrons with power supplies coupled to a set of transmission lines guiding the beams to the four upper and the equatorial launcher. The front steering upper launcher design described herein has passed successfully the preliminary design review, and it is presently in the final design stage. The launcher consists of a millimeter wave system and steering mechanism with neutron shielding integrated into an upper port plug with the plasma facing blanket shield module (in-vessel) and a set of ex-vessel waveguides connecting the launcher to the transmission lines.Part of the transmission lines are the ultra-low loss CVD torus diamond windows and a shutter valve, a mitre bend section and the feedthroughs integrated in the plug closure plate. These components are connected by corrugated waveguides and form together the first confinement system (FCS). In-vessel, the mm-wave system includes a quasi-optical beam propagation system including four mirror sets and a front steering mirror. The millimeter wave system is integrated into a specifically optimized upper port plug providing structural stability to withstand plasma disruptions forces and the high heat load from the plasma side with a dedicated blanket shield module. A recent update in the ITER interface definition has resulted in the recession of the upper port plug first wall panels, which is now integrated into the design. Apart from the millimeter wave system the upper port plug houses also a set of shield blocks which provide neutron shielding. An overview of the actual ITER ECRH upper launcher is given together with some highlights of the design.

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“…The design development is based on the preliminary design of the four upper launchers [1] and the actual intermediate design is shown in figure 2.…”

Section: Design Statusmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Progress of the ECRH Upper Launcher design for ITER

Strauß

Aiello

Bruschi

et al. 2014

Fusion Engineering and Design

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“…The four Upper port ECRH Launchers (UL) will couple up to 8 MW of electron-cyclotron heating power each into a dedicated target in the plasma [7]. The SMA is a critical component with a weight of 45 kg, and an acentric Center-of-Gravity (CoG).…”

Section: Example: Ul Steering Mirror Replacement Rhcamentioning

confidence: 99%

Analysis of ITER upper port plug remote handling maintenance scenarios

Koning

Baar

Elzendoorn

et al. 2012

Fusion Engineering and Design

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“…This means that the thickness of the disc must be an integer multiple of half the wavelength of the beam inside the material. Moveable mirrors are so used to deploy the beam at different locations, as in the ITER electron cyclotron H&CD system [2].…”

Section: Introductionmentioning

confidence: 99%

CVD diamond Brewster window: feasibility study by FEM analyses

Aiello

Grossetti

Meier

et al. 2012

EPJ Web of Conferences

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Abstract. Chemical vapor deposition (CVD) diamond windows are a crucial component in heating and current drive (H&CD) applications. In order to minimize the amount of reflected power from the diamond disc, its thickness must match the desired beam wavelength, thus proper targeting of the plasma requires movable beam reflectors. This is the case, for instance, of the ITER electron cyclotron H&CD system. However, looking at DEMO, the higher heat loads and neutron fluxes could make the use of movable parts close to the plasma difficult. The issue might be solved by using gyrotrons able to tune the beam frequency to the desired resonance, but this concept requires transmission windows that work in a given frequency range, such as the Brewster window. It consists of a CVD diamond disc brazed to two copper cuffs at the Brewster angle. The brazing process is carried out at about 800°C and then the temperature is decreased down to room temperature. Diamond and copper have very different thermal expansion coefficients, therefore high stresses build up during the cool down phase that might lead to failure of the disc. Considering also the complex geometry of the window with the skewed position of the disc, analyses are required in the first place to check its feasibility. The cool down phase was simulated by FEM structural analyses for several geometric and constraint configurations of the window. A study of indirect cooling of the window by water was also performed considering a HE 11 mode beam. The results are here reported.

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Preliminary design of the ITER ECH upper launcher

Cited by 4 publications

References 19 publications

Progress of the ECRH Upper Launcher design for ITER

Progress of the ECRH Upper Launcher design for ITER

Analysis of ITER upper port plug remote handling maintenance scenarios

CVD diamond Brewster window: feasibility study by FEM analyses

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