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 confined 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 i…
Preprint PublishedV. 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…
Preprint PublishedA Quadling WE Lee J Astbury
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 g…
PublishedV. 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
Preprint PublishedLi 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 PublishedM. 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 PurchaseA 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 PublishedW. McCarthy T. Golfinopoulos K.B. Woller C. Vincent A. Kuang B. Labombard
For the first time, a digital Mirror Langmuir probe (MLP) has successfully
Preprint PublishedEmil T. Jonasson Luis Ramos Pinto Alberto Vale Robert Skilton
Sensor technologies will play a key role in the success of Remote Maintenance (RM) systems for future fusion reactors such as ITER and DEMO. Understanding their limitations and suitability for use in a fusion context is crucial to the operation and maintenance of these reactors. In this paper, we evaluate three key types of sensor which are of p…
Preprint PublishedS. 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 scal…
Preprint Published