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UKAEA-CCFE-PR(21)462021
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
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UKAEA-CCFE-PR(21)382021
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 …
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UKAEA-CCFE-PR(23)882020
The pellet cycle of a mixed isotope tokamak plasma is successfully reproduced with reduced turbulent transport modelling within an integrated simulation framework. In JET tokamak experiments, deuterium pellets with reactor-relevant deposition characteristics were injected into a pure hydrogen plasma. Measurements of the isotope ratio profile inf…
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UKAEA-CCFE-PR(20)932020
Parametric dependencies of the linear stability of toroidal Alfven eigenmode (TAE) in the presence of neutral beam injection (NBI) are investigated to understand the beam drive and damping effect of TAEs in JET and KSTAR. It is found that the results depend on the drift orbit width of the beam-ions normalized to the characteristic mode widths. I…
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UKAEA-CCFE-PR(20)232019
To ensure optimal plasma performance at high Qfus for the baseline scenario foreseen for the International Tokamak Experimental Reactor (ITER), fuelling requirements, in particular for non-stationary phases, need to be assessed by means of integrated modelling due to different expected fuelling behaviour and additional challenges that need to be ad…
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UKAEA-CCFE-PR(20)172019
Core turbulent particle transport with multiple isotopes can display observable differences in behaviour between the electron and ion particle channels. Experimental observations at JET with mixed H-D plasmas and varying NBI and gas-puff sources [M. Maslov et al., Nucl. Fusion 7 076022 (2018)] inferred source dominated electr…
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UKAEA-CCFE-CP(19)472019
Spherical Tokamaks (STs) could provide a route towards a compact fusion reactor due to advantageous properties such as high plasma beta. A GW-scale ST plasma is explored where Q=10 and R=2.5m. In this design 110 MW of NBI is needed to provide 9 MA of noninductive current, where the remaining 12 MA is pressure driven. To penetrate into the core a 1 …
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UKAEA-CCFE-PR(19)752019
The evolution of the JET high performance hybrid scenario, including central accumulation of the tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based models. 8 transport channels are modelled predictively, with self-consistent sources, radiation and magne…
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UKAEA-CCFE-CP(18)022018
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UKAEA-CCFE-CP(19)272018
The ability to describe the essential physics and technology elements needed to robustly simulate the operation of ITER is critical to being able to model the plasma scenarios that will run in ITER. In this paper, the Integrated Modelling & Analysis Suite (IMAS) is used to simulate the 15 MA DT baseline scenario operation, including a descripti…
Showing 11 - 20 of 28 UKAEA Paper Results