Design, performance and construction of a 2MW ion beam test facility for plasma facing components

Greuner, H.; Bolt, H.; Böswirth, B.; Franke, T.; McNeely, P.; Obermayer, S.; Rust, N.; Süß, Rosmarie

doi:10.1016/j.fusengdes.2005.06.021

Cited by 47 publications

(31 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The excellent heat removal capability was demonstrated in previous test campaigns of more than 30 full-scale pre-series elements [7,8]. No large detachment or loss of CFC tiles occurred during previous cyclic loading tests performed in the neutral beam facility GLADIS [9], but growing local degradation of bonding at the free edges of several CFC tiles was observed. Therefore a detailed nonlinear thermo-mechanical FEM analysis of the CFC/Cubonding system was carried out with a view to achieving a reduction of the stress at this interface [10].…”

Section: Introductionmentioning

confidence: 58%

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

Self Cite

View full text Add to dashboard Cite

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.

show abstract

Section: Introductionmentioning

confidence: 58%

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

Self Cite

View full text Add to dashboard Cite

show abstract

“…[75,76] The cooling media was water at RT with 10 bar, a flow velocity of 10 m s -1 and a flow rate of It can be concluded that, even in such an extreme condition of a W laminate pipe surrounding an austenitic steel pipe, the W laminate pipe can excellently deal with the thermal mismatch and that testable mockups can be produced.…”

Section: Results Of Hhf Tests With Plasma Heat (Performed At Ipp Garcmentioning

confidence: 99%

Tungsten (W) Laminate Pipes for Innovative High Temperature Energy Conversion Systems

et al. 2014

View full text Add to dashboard Cite

The aim of this paper is to present the mechanical properties of tungsten laminate pipes made of tungsten foil and to discuss their use in innovative high temperature energy conversion systems.Tungsten is the metal with the highest melting point of all metals and would therefore be an excellent fit for high temperature applications. But tungsten has one major drawback which is its low fracture toughness at room temperature (RT) or its high brittle-to-ductile transition 2 temperature (BDTT). However, one of the extraordinary properties of tungsten is that by cold working the BDTT can be shifted to lower temperatures. At the extreme, this results in a tungsten foil with a BDTT below -120°C combined with a RT fracture toughness of 70 MPa m 1/2 .By rolling up and joining a tungsten foil, tungsten laminate pipes can be synthesized that can dissipate at least 20 J in a Charpy impact test at RT and survive a burst test at RT at 1000 bar without any residual damage. The technical maturity of these W laminate pipes is approved by high heat flux tests performed at the Plataforma Solar de Almería, Spain, as well as at the

show abstract

“…The target water-cooling parameters of the facility are: maximal flow rate 8.5 l/s, water inlet temperature 20 °C and a static pressure up to 1.6 MPa. More technical characteristics are described in detail in the literature [10,11]. A hydrogen beam (20-30 keV) generates the heat load.…”

Section: High Heat Flux Testsmentioning

confidence: 99%

Design and evaluation of an optimized W/Cu interlayer for W monoblock components

Herrmann

Greuner

Balden

et al. 2011

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Divertor plasma-facing components of future fusion reactors should be able to withstand heat fluxes of 10-20 MW/m² in stationary operation. Tungsten blocks with an inner cooling tube made of CuCr1Zr, so-called monoblocks, are potential candidates for such water-cooled components. To increase the strength and reliability of the interface between the W and the cooling tube of a Cu-based alloy (CuCr1Zr), a novel advanced W-fibre/Cu metal matrix composite (MMC) was developed for operation temperatures up to 550°C. Based on optimization results to enhance the adhesion between fibre and matrix, W fibres (W f ) were chemically etched, coated by physical vapour deposition with a continuously graded W/CuPVD interlayer and then heated to 800°C. The W f /Cu MMC was implemented by hot-isostatic pressing and brazing process in monoblock mock-ups reinforcing the interface between the plasma-facing material and the cooling channel. The suitability of the MMC as an efficient heat sink interface for water-cooled divertor components was tested in the high heat flux (HHF) facility GLADIS. Predictions from finite element simulations of the thermal behaviour of the component under loading conditions were confirmed by the HHF tests. The W f /Cu MMC interlayer of the mock-ups survived cyclic heat loads above 10 MW/m² without any damage. One W block of each tested mock-up showed stable thermal behaviour at heat fluxes of up to 10.5 MW/m².

show abstract

Design, performance and construction of a 2MW ion beam test facility for plasma facing components

Cited by 47 publications

References 3 publications

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

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

Tungsten (W) Laminate Pipes for Innovative High Temperature Energy Conversion Systems

Design and evaluation of an optimized W/Cu interlayer for W monoblock components

Contact Info

Product

Resources

About