英国物理学会
期刊
会议
图书
作者:M Lipa , G Pintsuk
来源:[J].Physica Scripta, 2016, Vol.2016 (T167)IOP
摘要:The W—for tungsten—Environment in Steady-state Tokamak (WEST) project is based on an upgrade of the Tore Supra tokamak from a carbon limiter to an X -point divertor device. A new set of actively cooled tungsten coated plasma facing components will cover a part of the vessel ...
作者:M Lipa , A Martinez ...
来源:[J].Physica Scripta, 2016, Vol.2016 (T167)IOP
摘要:After a brief introduction giving some insight of the WEST project, we present the three types of plasma facing units (PFUs) developed for the WEST project taking into account the envisaged main scenarios: (1) high power short pulse scenario (a few seconds) where the objecti...
作者:M Lipa , M Missirlian ...
来源:[J].Physica Scripta, 2016, Vol.2016 (T167)IOP
摘要:The primary goal of the WEST project is to be a test bed to characterize the fatigue and lifetime of ITER-like W divertor components subjected to relevant thermal loads. During the first phase of exploitation (S2 2016), these components (W monoblock plasma facing unit—W-PFU)...
作者:M Lipa , M Missirlian
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:M Lipa , M Missirlian
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...

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