Showing 1 - 10 of 408 Journals Results
2021
UKAEA-CCFE-PR(21)62
B. Dudson S. L. Newton J. T. Omotani J. Birch
Drift-reduced MHD models are widely used to study magnetised plasma phenomena, in particular for magnetically con ned fusion applications, as well as in solar and astrophysical research. This letter discusses the choice of Ohm’s law in these models, the resulting dispersion relations for the dynamics parallel to the magnetic field, and the impli…
Preprint2021
UKAEA-CCFE-PR(21)61
V. H. Hall-Chen F. I. Parra J. C. Hillesheim
We use beam tracing — implemented with a newly-written code, Scotty — and the reciprocity theorem to derive a model for the linear backscattered power of the Doppler Backscattering (DBS) diagnostic. Our model works for both the O-mode and X-mode in tokamak geometry (and certain regimes of stellarators). We present the analytical derivation of o…
Preprint2021
UKAEA-CCFE-PR(21)52
A Quadling Director of Materials UK Atomic Energy AuthorityWE Lee Ser Cymru Professor of Materials in Extreme Environments Nuclear Futures Institute Bangor University.J Astbury Reactor Technology Manager & Head of Neutronics Tokamak Energy
Fusion has entered the engineering era. Moving from plasma science to experiments demonstrating the benefits of modified torus shapes and advanced divertor geometries, the ‘field’ has become an ‘industry’. Investors focus now on whether superconducting magnet joints are feasible in large tokamak designs and how to deliver net energy to grid…
Preprint2021
UKAEA-CCFE-PR(21)46
V. K. Zotta L. Garzotti F. J. Casson D. Frigione F. Koechl E. Lerche P. Lomas F. Rimini M. Sertoli D. Van Eester R. Gatto C. Mazzotta G. Pucella
The fusion performance of ELMy H-mode DT plasmas with q95 = 3 and \\beta_N = 1.8 (also referred to as medium-\\beta_N baseline scenario in the rest of this paper) are predicted with the JINTRAC suite of codes and the QuaLiKiZ transport model. The predictions are based on the analysis of DT plasmas from the first DT campaign on JET in 1997 (DTE1…
Preprint2021
UKAEA-CCFE-PR(21)39
Li Li Yueqiang Liu Guoliang Xia Y. F. Wang Q. B. Luan W. D. Zhang F. C. Zhong
A recently updated version of the MARS-F code [Y. Q. Liu et al. Phys. Plasmas 7, 3681 (2000); L. Li et al. Phys. Plasmas 25, 082512 (2018); G. L. Xia et al. Nucl. Fusion 59, 126035 (2019)] is utilized to numerically investigate the plasma screening effect on the applied resonant magnetic perturbation (RMP) field, assuming various equilibrium flo…
Preprint Published2021
UKAEA-CCFE-PR(21)38
M. Brank R. A. Pitts G. Simič P. Lamalle M. Kocan F. Koechl Y. Gribov V. Polli L. Kos
Ion cyclotron resonance heating (ICRH) is one of the three additional heating schemes to be deployed on ITER. Its two antenna arrays, installed on the outboard midplane, will deliver 20 MW of RF power in the 40-55 MHz frequency range. The plasma-facing component of …
Preprint Purchase2021
UKAEA-CCFE-PR(21)35
A R Field P Carvalho D Frigione L Garzotti Hyun-Tae Kim M Lenholm E Lerche J Mailloux F Rimini C M Roach M Sertoli G Szepeisi D van Eester.
Sustained operation of high-performance, ITER-baseline scenario plasmas at the high levels of input power (~< 40MA) required to achieve ~ 15 MW of D-T fusion power in JET-ILW requires careful optimisation of the fuelling to avoid an unacceptable disruption rate due to excessive radiation, primarily from W impurities, which are sputter…
Preprint Published2021
UKAEA-CCFE-PR(21)32
W. McCarthy T. Golfinopoulos K.B.Woller C. Vincent A. Kuang B. Labombard
For the first time, a digital Mirror Langmuir probe (MLP) has successfully sampled plasma temperature, ion saturation current, and floating potential together on a single probe tip in real time in a radio-frequency driven helicon linear plasma device. This is accomplished by feedback control of the bias sweep to ensure a good fit to I-V charact…
Preprint2021
UKAEA-CCFE-PR(21)19
S. H. Ward R. Akers A. Jacobsen P. Ollus S. D. Pinches E. Tholerus R. G. L. Vann M. A. Van Zeeland
A novel high-performance computing algorithm, developed in response to the next generation of computational challenges associated with burning plasma regimes in ITER-scale tokamak devices, has been tested and is described herein. LOCUST-GPU 2 The Lorentz-Orbit Code for Use in Stellarators and Tokamaks (LOCUST) is designed for computationally s…
Preprint2021
UKAEA-CCFE-PR(21)08