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作者:S.P. Gerhardt , J.E. Menard ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (8)
摘要:During the 2016 NSTX-U experimental campaign, locked modes in the plasma edge presented clear evidence of the presence of error fields. Extensive metrology and plasma response modeling with IPEC and M3D-C1 have been conducted to understand the various sources of error fields...
作者:S.P. Gerhardt , J.E. Menard
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (6)
摘要:This paper examines a method for real-time control of non-inductively sustained scenarios in NSTX-U by using TRANSP, a time-dependent integrated modeling code for prediction and interpretive analysis of tokamak experimental data, as a simulator. The actuators considered for contr...
作者:... E.D. Fredrickson , S.P. Gerhardt , R.B. White
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (5)
摘要:Neutral beam injection (NBI) is one of the primary tools foreseen for heating, current drive (CD) and q-profile control in future fusion reactors such as ITER and a Fusion Nuclear Science Facility. However, fast ions from NBI may also provide the drive for energetic particle...
作者:S.P. Gerhardt , R.S. Granetz ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (6)
摘要:A multi-device database of disruption characteristics has been developed under the auspices of the International Tokamak Physics Activity magneto-hydrodynamics topical group. The purpose of this ITPA disruption database (IDDB) is to find the commonalities between the disruption a...
作者:S.P. Gerhardt , B.P. LeBlanc
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (12)
摘要:Marginal stability points of global modes during high plasma pressure operation in the National Spherical Torus Experiment (NSTX) device can be found by computing kinetic modifications to ideal magnetohydrodynamic limits on stability. Calculations with the DCON code for nearly fi...
作者:S.P. Gerhardt , D. Mueller
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (12)
摘要:One of the goals of the National Spherical Torus Experiment Upgrade (NSTX-U) (Menard et al 2012 Nucl. Fusion 52 083015) is the demonstration of fully non-inductive start-up, current ramp-up and sustainment. This work discusses predictive simulations where the available heating an...
作者:S.P. Gerhardt , D. Green ...
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (1)
摘要:Several experiments on different machines and in different fast wave (FW) heating regimes, such as hydrogen minority heating and high harmonic fast waves (HHFW), have found strong interaction between radio-frequency (RF) waves and the scrape-off layer (SOL) region. This pape...
作者:S.P. Gerhardt , M.D. Boyer ...
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (3)
摘要:A model-based feedback system is presented to control plasma rotation in a magnetically confined toroidal fusion device, to maintain plasma stability for long-pulse operation. This research uses experimental measurements from the National Spherical Torus Experiment (NSTX) and is ...
作者:S.P. Gerhardt , E.V. Belova ...
来源:[J].Nuclear Fusion(IF 2.734), 2008, Vol.48 (3)
摘要:A new method for inductively forming a field reversed configuration is demonstrated, based on the inductively driven transformation of a spheromak. The driven transition can be achieved in argon and krypton plasmas, in which MHD modes are suppressed; simulations indicate that sta...
作者:S.P. Gerhardt , J.E. Menard , the NSTX Team
来源:[J].Nuclear Fusion(IF 2.734), 2009, Vol.49 (2)
摘要:A detailed analysis of the plasma current quench in the National Spherical Torus Experiment (Ono et al 2000 Nucl. Fusion 40 557 ) is presented. The fastest current quenches are fit better by a linear waveform than an exponential one. Area-normalized current quench tim...

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