A. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
Preprint PublishedA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed. The assessment is performed on the basis of empirical and…
Preprint PublishedJ. Simpson D. Moulton C. Giroud D. Harting G. Corrigan M. Groth JET Contributors
EDGE2D-EIRENE simulations of upstream density and radiative power scans in JET H-mode type plasmas in vertical target predict a linear relationship between the electron and ion temperatures, and power across the separatrix. This is in contradiction to the two-point model equations which states that the upstream temperature scales at the po…
Preprint PublishedF. Koechl R. Ambrosino P. Belo M. Cavinato G. Corrigan L. Garzotti D. Harting A. Kukushkin A. Loarte M. Mattei E. Militello-Asp V. Parail M. Romanelli G. Saibene R. Sartori
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…
Preprint PublishedK D Lawson M Groth D Harting S Menmuir D Reiter K M Aggarwal S Brezinsek I H Coffey G Corrigan F P Keenan C F Maggi A G Meigs M G O’Mullane S Wiesen JET Contributors
An understanding of the plasma edge and divertor is essential for predicting the performance of next-step machines such as ITER. Transport codes used to study the divertor behaviour [1] employ atomic physics data in two applications. The first is to predict the power radiated by the fuel and impurity atoms, which is carried out as a post-processing…
Preprint PublishedF. Koechl S.D. Pinches F.J. Casson G. Corrigan Y. Gribov D. Harting A.A. Kavin R.R. Khayrutdinov S.-H. Kim P.J. Knight S.V. Konovalov A. Loarte V.E. Lukash S. Medvedev A.R. Polevoi
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…
Preprint PublishedL. Horvath C.F. Maggi A. Chankin S. Saarelma A.R. Field E. Belonohy A. Boboc G. Corrigan E.G. Delabie J. Flanagan L. Frassinetti C. Giroud D. Harting D. Keeling D. King M. Maslov G.F. Matthews S. Menmuir S.A. Silburn J. Simpson A.C.C Sips H. Weisen K.J. Gibson JET Contributors
The pedestal structure, ELM losses and linear MHD stability are analysed in a series of JET-ILW H and D type I ELMy H-mode plasmas. The pedestal pressure (pPED) is typically higher in D than in H at the same input power, with the difference mainly due to lower density in H than in D. At the same input power, the pedestal electron pres…
Preprint PublishedE. Militello Asp G. Corrigan P. da Silva Aresta Belo L. Garzotti D.M. Harting F. Köchl V. Parail M. Cavinato A. Loarte M. Romanelli R. Sartori
We have modelled self-consistently the most efficient ways to fuel ITER Hydrogen (H), Helium (He) and Deuterium-Tritium (DT) plasmas with gas and/or pellet injection with the integrated core and 2D SOL/divertor suite of codes JINTRAC. As far as we are aware, for ITER this is the first time modelling of the entire plasma has been carried out to f…
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