英国物理学会
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作者:B Böswirth , T Eich ...
来源:[J].Physica Scripta, 2014, Vol.2014 (T159)IOP
摘要:Fast infrared (IR) thermography resolves the transient edge localized mode (ELM) induced heat fluxes on divertor components on time scales of a few hundred microseconds. These heat loads range from 10 to several 100 MW m−2 and energy densities of 15–200 kJ m<...
作者:B Böswirth , S Elgeti (Lindig) ...
来源:[J].Physica Scripta, 2014, Vol.2014 (T159)IOP
摘要:We investigated the erosion behaviour of tungsten under irradiation with a fusion reactor-relevant H/He mixture of 94%/6% at a power density of 10 MW m−2. The investigated surface temperatures range up to 2000 °C and the range of the applied fluence was up to 7 × ...
作者:B Böswirth , M Balden ...
来源:[J].Physica Scripta, 2016, Vol.2016 (T167)IOP
摘要:The kinetics of tungsten carbide formation was investigated for tungsten coatings on carbon fibre composite with a molybdenum interlayer as they are used in the ITER-like Wall in JET. The coatings were produced by combined magnetron sputtering and ion implantation. The inves...
作者:B Böswirth , M Lipa ...
来源:[J].Physica Scripta, 2017, Vol.2017 (T170)IOP
摘要:One goal of the WEST project (W Environment in Steady-state Tokamak) is the manufacturing, quality assessment and operation of ITER-like actively water-cooled divertor plasma facing components made of tungsten. Six W monoblock plasma facing units (PFUs) from different suppli...
作者:B Böswirth , M Lipa ...
来源:[J].Physica Scripta, 2017, Vol.2017 (T170)IOP
摘要:One goal of the WEST project (W Environment in Steady-state Tokamak) is the manufacturing, quality assessment and operation of ITER-like actively water-cooled divertor plasma facing components made of tungsten. Six W monoblock plasma facing units (PFUs) from different suppli...
作者:B Böswirth , H Greuner ...
来源:[J].Physica Scripta, 2017, Vol.2017 (T170)IOP
摘要:In the field of fusion experiments using a tokamak, the plasma facing components (PFC) are the closest object to the hot plasma. Due to the plasma-wall interaction, the material composing the PFC may enter the plasma and disturb the experiments. In the past, the main material for...
作者:B Böswirth , I Chu ...
来源:[J].Physica Scripta, 2017, Vol.2017 (T170)IOP
摘要:The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. In DEMO, divertor targets must survive an environment of high heat fluxes (∼up to 20 MW m−2 during slow transients) and neutron irradiatio...
作者:B Böswirth , S Elgeti ...
来源:[J].Physica Scripta, 2017, Vol.2017 (T170)IOP
摘要:High heat flux tests have been performed on 0.4 mm thick W coatings produced by vacuum plasma spraying on carbon-fiber composites (CFCs) for the future actively cooled W-coated CFC divertor target in JT-60SA. The surface temperature of the W coating increased up to 2000 °C a...
作者:B Böswirth , M Balden ...
来源:[J].Physica Scripta(IF 1.032), 2009, Vol.2009 (T138), pp.014031 (5pp)IOP
摘要:This contribution summarizes the work that has been performed to establish the industrial production of tungsten coatings on carbon fibre composite (CFC) for application within the ITER-like Wall Project at JET. This comprises the investigation of vacuum plasma-sprayed coatings, ...
作者:B Böswirth , T Schindler
来源:[J].Physica Scripta(IF 1.032), 2009, Vol.2009 (T138), pp.014063 (4pp)IOP
摘要:An automated IR image processing method was developed to evaluate the surface temperature distribution of cyclically loaded high heat flux (HHF) plasma facing components. IPP Garching will perform the HHF testing of a high percentage of the series production of the WENDELSTEIN 7-...

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