英国物理学会
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作者:Sai Bharadwaj Vishnubhotla , Rimei Chen , Subarna R Khanal ...
来源:[J].Nanotechnology(IF 3.842), 2019, Vol.30 (4)IOP
摘要:Conductive modes of atomic force microscopy are widely used to characterize the electronic properties of materials, and in such measurements, contact size is typically determined from current flow. Conversely, in nanodevice applications, the current flow is predicted from the est...
作者:P. Barabaschi , Y. Kamada , H. Shirai ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The JT-60SA project was initiated in June 2007 under the framework of the Broader Approach Agreement and Japanese National Fusion Programme for an early realization of fusion energy by conducting supportive and complementary work for the ITER project towards supporting the basis ...
作者:G. Zhuang , G.Q. Li , J. Li ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to eventually reach DEMO relevant power level 1 GW, to manifest a high duty factor of 0.3–0.5, and to pursue ...
作者:E.J. Strait , J.L. Barr , M. Baruzzo ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been demonstrated in recent research worldwide. Recent analysis has identified the current density profile as the main drive for disruptive ins...
作者:S.M. Kaye , D.J. Battaglia , D. Baver ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The mission of the spherical tokamak NSTX-U is to explore the physics that drives core and pedestal transport and stability at high- and low collisionality, as part of the development of the spherical tokamak (ST) concept towards a compact, low-cost ST-based pilot plant. NSTX-U w...
作者:T. Klinger , T. Andreeva , S. Bozhenkov ...
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:B. Bigot
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:ITER reached 50% completion of the work required to achieve First Plasma in November 2017. Progress has been made on ITER infrastructure since the 2016 Fusion Energy Conference, most visibly the construction of many key buildings. The key parts of the tokamak assembly building an...
作者:R.L. Tanna , Harshita Raj , J. Ghosh ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The first Indian tokamak, ADITYA, operated for over two decades with a circular poloidal limiter, has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) to attain shaped-plasma operations with an open divertor in single and double-null configurations. Experimental re...
作者:C.C. Petty , the DIII-D Team
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:DIII-D research is addressing critical challenges in preparation for ITER and the next generation of fusion devices through focusing on plasma physics fundamentals that underpin key fusion goals, understanding the interaction of disparate core and boundary plasma physics, an...
作者:J.R. Harrison , R.J. Akers , S.Y. Allan ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The mega amp spherical tokamak (MAST) was a low aspect ratio device ( R / a = 0.85/0.65 ~ 1.3) with similar poloidal cross-section to other medium-size tokamaks. The physics programme concentrates on addressing key physics issues for the operation of ITER, design of DEMO and...

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