Showing 1 - 10 of 33 Journals Results
2021
UKAEA-CCFE-PR(21)58
M. Kong F. Felici O. Sauter C. Galperti T. Vu C. Ham T.C. Hender M. Maraschek M. Reich the TCV team the ASDEX Upgrade team the MAST team the EUROfusion MST1 team
This paper presents recent progress on the studies of neoclassical tearing modes (NTMs) on TCV, concerning the new physics learned and how this physics contributes to a better real-time (RT) control of NTMs. A simple technique that adds a small (sinusoidal) sweeping to the target electron cyclotron (EC) beam deposition location has proven effective…
Preprint2020
UKAEA-CCFE-PR(20)80
O. P. Bardsley T. C. Hender
Reduced activation ferritic steels are an attractive option for use in large structural components surrounding tokamak plasmas in future fusion power plants, but their ferromagnetic response to the confining magnetic fields must be properly understood. Simultaneously, the advantages of operating at high plasma elongation push tokamak designs tow…
Preprint Published2019
UKAEA-CCFE-PR(19)20
Sergei Gerasimov P. Abreu G Artaserse M. Baruzzo P. Buratti I.S. Carvalho I.H. Coffey E. de la Luna T.C. Hender R.B. Henriques R. Felton U. Kruezi P.J. Lomas P. McCullen M. Maslov E. Matveeva S. Moradi L. Piron F.G. Rimini W. Schippers G. Szepesi M. Tsalas L.E. Zakharov
The paper presents an analysis of disruptions occurring during JET-ILW plasma operations covering the period from the start of ILW (ITER-like wall) operation up to completion of JET operation in 2016. The total number of disruptions was 1951 including 466 with deliberately induced disruptions. The average disruption rate of unintended disruptions i…
Preprint Published2016
CCFE-PR(16)32
J.E. Menard T. Brown L. El-Guebaly M. Boyer J. Canik B. Colling R. Raman Y. Zhai P. Buxton B. Covele C. D'Angelo A. Davis S. Gerhardt M. Gryaznevich M. Harb T.C. Hender S. Kaye D. Kingham M. Kotschenreuther S. Mahajan R. Maingi E. Marriott E.T. Meier L. Mynsberge C. Neumeyer M. Ono S.A. Sabbagh V. Soukhanovskii P. Valanju R. Woolley
A Fusion Nuclear Science Facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The spherical torus/tokamak (ST) is a leading candidate for an FNSF due to its potentially high neutron wall loading and modular configuration. A key consid…
Preprint Published2016
CCFE-PR(16)25
Y. Liu S.A. Sabbagh I.T. Chapman S. Gerasimov Y. Gribov T.C. Hender V. Igochine M. Maraschek G. Matsunag M. Okabayashi E.J. Strait
The high-frequency noise measured by magnetic sensors, at levels above the typical frequency of resistive wall modes, is analyzed across a range of present tokamak devices including DIII-D, JET, MAST, ASDEX Upgrade, JT-60U, and NSTX. A high-pass filter enables identification of the noise component with Gaussian-like statistics that shares certain c…
Preprint Purchase2015
CCFE-PR(15)30
S.N. Gerasimov P. Abreu M. Baruzzo V. Drozdov A. Dvornova J. Havlicek T.C. Hender O. Hronova U. Kruezi X. Li T. Markovič R. Pánek G. Rubinacci M. Tsalas S. Ventre F. Villone L.E. Zakharov JET Contributors
Asymmetrical disruptions may occur during ITER operation and they may be accompanied by large sideways forces and rotation of the asymmetry. This is of particular concern because resonance of the rotating asymmetry with the natural frequencies of the vacuum vessel (and other in-vessel components) could lead to large dynamic amplification of the for…
Preprint Published2014
S.N. Gerasimov T.C. Hender J. Morris V. Riccardo L.E. Zakharov JET EFDA Contributors
A key feature of disruptions during Vertical Displacement Events (VDEs), discovered in JET in 1996, is the toroidal variation in the measured plasma current Ip, i.e. the plasma current asymmetries, lasting for almost the entire current quench. The unique magnetic diagnostics at JET (full set of poloidal coils and saddle loops recorded either from t…
Published2013
C.J. Ham J.W. Connor S.C. Cowley R.J. Hastie T.C. Hender Y.Q. Liu
Calculations of tearing mode stability in tokamaks split conveniently into an external region, where marginally stable ideal MHD is applicable, and a resonant layer around the rational surface where sophisticated kinetic physics is needed. These two regions are coupled by the stability parameter △'. Pressure and current perturbations local…
Published2012
C. D. Warrick R. J. Buttery G. Cunningham S. J. Fielding T. C. Hender B. Lloyd A.W. Morris M. R. O’Brien T. Pinfold K. Stammers M. Valovic M. Walsh,* H. R. Wilson Compass-D Rf Teams
Lower hybrid current drive (LHCD) with modest powers ( 10% of the total power input) has been used for the first time to completely stabilize performance limiting neoclassical tearing modes in many COMPASS-D tokamak discharges. The stabilizing effect in these experiments is consistent with a reduction in the free energy available in the current pro…
Published2012