英国物理学会
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作者:S. Bozhenkov , T. Bräuer ...
来源:[J].Journal of Instrumentation(IF 1.869), 2015, Vol.10 (10)IOP
摘要:Wendelstein 7-X (W7-X) is a large optimized stellarator (B=2.5T, V=30m3) aiming at demonstrating the reactor relevance of the optimized stellarators. In 2015 W7-X will begin its first operation phase (OP1.1) with five inertially cooled inboard limiters made of graphite...
作者:S. Bozhenkov , F. Effenberg ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (12)IOP
摘要:Wendelstein 7-X (W7-X) is currently under commissioning in preparation for its initial plasma operation phase, operation phase 1.1 (OP1.1). This first phase serves primarily to provide an integral commissioning of all major systems needed for plasma operation, as well as systems,...
作者:S. Bozhenkov , R. König ...
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (2)IOP
摘要:The edge topology of magnetic fusion devices is decisive for the control of the plasma exhaust. In Wendelstein 7-X, the island divertor concept will be used, for which the edge topology can change significantly as the internal currents in a plasma discharge evolve towards steady-...
作者:S. Bozhenkov , S. Brezinsek ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (5)IOP
摘要:During the first operational phase (referred to as OP1.1) of the new Wendelstein 7-X (W7-X) stellarator, five poloidal graphite limiters were mounted on the inboard side of the vacuum vessel, one in each of the five toroidal modules which form the W7-X vacuum vessel. Each li...
作者:S. Bozhenkov , U. Höfel ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (8)IOP
摘要:Observations on confinement in the first experimental campaign on the optimized Stellarator Wendelstein 7-X are summarized. In this phase W7-X was equipped with five inboard limiters only and thus the discharge length restricted to avoid local overheating. Stationary plasmas...
作者:S. Bozhenkov , R. Brakel ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (10)IOP
摘要:After completing the main construction phase of Wendelstein 7-X (W7-X) and successfully commissioning the device, first plasma operation started at the end of 2015. Integral commissioning of plasma start-up and operation using electron cyclotron resonance heating (ECRH) and ...
作者:S. Bozhenkov , C. Brandt ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The optimized superconducting stellarator device Wendelstein 7-X (with major radius , minor radius , and plasma volume) restarted operation after the assembly of a graphite heat shield and 10 inertially cooled island divertor modules. This paper reports on the results from the f...
作者:... T.S. Pedersen , S. Bozhenkov , W7-X Team
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (1)IOP
摘要:The distribution of particles and power flux to plasma-facing components play a critical role in the design of next-generation fusion devices. In particular, it is a challenge to bring down the peak heat fluxes onto the divertor to manageable levels (of order 5 MW ). A large valu...
作者:S. Bozhenkov , A. Dinklage ...
来源:[J].Nuclear Fusion(IF 2.734), 2013, Vol.53 (11)IOP
摘要:The purpose of this study is the investigation of the non-linear plasma response of transport due to stochastic effects. On the Large Helical Device, perturbation coils create a resonant magnetic perturbation (RMP) with the m / n = 1/1 and 2/1 Fourier components. Depending on the...

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