The capabilities of steady state operation at the stellarator W7-X with emphasis on divertor design

Renner, H.; Boscary, J.; Erckmann, V.; Greuner, H.; Grote, H.; Sapper, J.; Speth, E.; Wesner, F.; Wanner, M.; Team, W X

doi:10.1088/0029-5515/40/6/306

Cited by 89 publications

(92 citation statements)

References 10 publications

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“…The development of the WENDELSTEIN 7-X (W7-X) divertor aims to manufacture roughly 900 plasma facing components (PFCs) that fulfil all requirements of reliable long pulse and longterm operation [1]. These nearly 20m²of activelywater-cooled PFCs, the so-called targets, are made of CFC NB31 (Snecma Propulsion Solide) as plasma facing material bonded by an Active Metal Casting® (registered by PLANSEE, AMC) copper interlayer onto a water-cooled CuCrZr structure [2].…”

Section: Introductionmentioning

confidence: 99%

Review of the high heat flux testing as an integrated part of W7-X divertor development

Greuner

Böswirth

Boscary

et al. 2009

Fusion Engineering and Design

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The subject of the development of the WENDELSTEIN 7-X divertor is the manufacturing of approximately 900 plasma facing components (PFCs) that meet all requirements for reliable long pulse and long-term plasma operation. The actively cooled PFCs are made of CFC NB31 as plasma facing material bonded by Active Metal Casting® (AMC) copper interlayer onto CuCrZr cooling structure. The pre-series activities integrated extensive high heat flux (HHF) testing to assess the industrial manufacturing. Tests were performed in the GLADIS facility under load conditions similar to those expected during operation of W7-X. The investigations focused on the improvement of fatigue resistance of the CFC/Cu bonding. The results of the last HHF test campaign demonstrated a significant enhancement of the CFC bonding quality due to the introduction of the AMC/Cu bi-layer technology. The results of the micro-chemical analyses (using EDX, AES, XPS and SIMS) of the CFC/Cu interface performed after 5000 cycles at 10MW/m² confirmed its chemical stability. Far beyond the current available data about the expected lifetime of CFC-armoured PFCs, 10,000 cycles at 10MW/m² were applied without any damages at the interface. The present design and manufacturing process of the tested PFCs fulfil all requirements for W7-X operation.

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Section: Introductionmentioning

confidence: 99%

Review of the high heat flux testing as an integrated part of W7-X divertor development

Greuner

Böswirth

Boscary

et al. 2009

Fusion Engineering and Design

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“…The aim of the extensive high heat flux (HHF) test campaigns was to establish the industrial process for the manufacturing of 890 targets, which will be needed for the installation of the 19 m2 highly loaded divertor area in WENDELSTEIN 7-X (W7-X) [1]. The target design is based on flat tiles made of CFC NB31 [2][3][4] as plasma facing material bonded by Active Metal Casting (AMC) [5] onto a water-cooled CuCrZr structure [6].…”

Section: Introductionmentioning

confidence: 99%

Cyclic heat load testing of improved CFC/Cu bonding for the W 7-X divertor targets

Greuner

Böswirth

Boscary

et al. 2009

Journal of Nuclear Materials

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Extensive high heat flux cycling testing of pre-series targets was performed in the neutral beam facility GLADIS to establish the industrial process for the manufacturing of 890 targets, which will be needed for the installation of the WENDELSTEIN 7-X divertor. The targets are manufactured of flat tiles of CFC NB31 as plasma facing material bonded by an Active Metal Casting copper interlayer onto a water-cooled CuCrZr structure. Based on the results of the 3D thermo-mechanical FEM analysis of the CFC/Cu interface, an additional set of 17 full-scale pre-series elements including three design variations was manufactured by PLANSEE SE. The insertion of an additional plastically compliant copper interlayer between the cooling structure and the Active Metal Casting interlayer showed the best results. No critical tile detachment was observed during >5000 cycles at 10 MW/m². These results demonstrated the sufficient life time of the component for the expected heat load in operation.

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“…The stellarator experiment W7-X being constructed in Greifswald, Germany, is designed for stationary plasma operation (30 min) with steady state heating of up to 10 MW ECRH and 10 s pulse heating power of up to 20 MW with additional NBI and ICRH [1]. The PFCs [2,3] as shown in figure 1 comprise the divertor targets (shown in magenta), baffles (brown), heat shields (blue), wall panels (cyan) and minor others (grey).…”

Section: Introductionmentioning

confidence: 99%

Thermo-mechanical analysis of Wendelstein 7-X plasma facing components

Peng

Bykov

Köppen

et al. 2013

Fusion Engineering and Design

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The stellarator experiment Wendelstein 7-X (W7-X) is designed for stationary plasma operation (30 minutes). Plasma facing components (PFCs) such as the divertor targets, baffles, heat shields and wall panels are being installed in the plasma vessel (PV) in order to protect it and other invessel components. The different PFCs will be exposed to different magnitude of heat loads in the range of 100 kW/m2 to 10 MW/m2 during plasma operation. An important issue concerning the design of these PFCs is the thermo-mechanical analysis to verify their suitability for the specified operation phases. A series of finite element (FE) simulations has been performed to achieve this goal. Previous studies focused on the test divertor unit (TDU) and high heat flux (HHF) target elements. The paper presents detailed FE thermo-mechanical analyses of a prototype HHF target module, baffles, heat shields and wall panels, as well as benchmarking against tests. Xuebing PengMr.Max Planck Institute for Plasma Physics, EURATOM Association,Greifswald, Germany 14 September 2012 Dear Dr. Ing.Olaf, Please accept the attached manuscript of the paper, named Thermo-mechanical analysis of Wendelstein 7-X plasma facing components, for SOFT-27 special issue. The paper is about the thermo-mechanical analysis of Wendelstein 7-X plasma facing components, including the high heat flux divertor targets, baffles, heat shields and wall panels, in order to verify their suitability for steady state operation.I greatly appreciate you taking time to read this letter and the paper, and am look forward to hearing from you. Best regardsSincerely yours, Xuebing Peng. Cover Letter Research Highlights Thermo-mechanical analysis of HHF divertor module TM-H09 shows that it can withstand heat loads of 10 MW/m 2 in steady state when the supports was optimized accordingly.  FE calculations indicate that the tiles of baffles and heat shields can withstand stationary heat loads of 250 kW/m 2 , but that the pulse length of plasma operation must be limited depending on the number of full load (500 kW/m 2 ) cycles.  Gap requirements for wall panels during assembly were defined based on several FE calculations. The stellarator experiment Wendelstein 7-X (W7-X) is designed for stationary plasma operation (30 minutes). Plasma facing components (PFCs) such as the divertor targets, baffles, heat shields and wall panels are being installed in the plasma vessel (PV) in order to protect it and other in-vessel components. The different PFCs will be exposed to different magnitude of heat loads in the range of 100 kW/m 2 to 10 MW/m 2 during plasma operation. An important issue concerning the design of these PFCs is the thermo-mechanical analysis to verify their suitability for the specified operation phases. A series of finite element (FE) simulations has been performed to achieve this goal. Previous studies focused on the test divertor unit (TDU) and high heat flux (HHF) target elements. The paper presents detailed FE thermo-mechanical analyses of a prototype HHF target modu...

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The capabilities of steady state operation at the stellarator W7-X with emphasis on divertor design

Cited by 89 publications

References 10 publications

Review of the high heat flux testing as an integrated part of W7-X divertor development

Review of the high heat flux testing as an integrated part of W7-X divertor development

Cyclic heat load testing of improved CFC/Cu bonding for the W 7-X divertor targets

Thermo-mechanical analysis of Wendelstein 7-X plasma facing components

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