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Dependence of the boundary heat flux width on core and edge profiles in Alcator C-Mod

Ballinger, S.B.; Brunner, D.; Hubbard, Amanda E.; Hughes, Jerry W.; Kuang, Adam Q.; e.a. (IOP, 2022-01)

This work presents new evidence that the heat flux width, λ q , in the Alcator C-Mod tokamak scales with the edge electron pressure, as observed in the ASDEX Upgrade (AUG) tokamak (Silvagni et al 2020 Plasma Phys. Control. ...
Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a low-power scenario in the DTT

Moscheni, M.; Meineri, C.; Wigram, Mike; Carati, C.; De Marchi, E.; e.a. (IOP, 2021-11)

As reactor-level nuclear fusion experiments are approaching, a solution to the power exhaust issue in future fusion reactors is still missing. The maximum steady-state heat load that can be exhausted by the present technology ...
Development and experimental qualification of novel disruption prevention techniques on DIII-D

Barr, J.L.; Sammuli, B.; Humphreys, D.A.; Olofsson, E.; Du, X.D.; e.a. (IOP, 2021-08)

Novel disruption prevention solutions spanning a range of control regimes are being developed and tested on DIII-D to enable ITER success. First, a new real-time control algorithm has been developed and tested for regulating ...

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