Showing 1 - 10 of 15 Journals Results
2019
UKAEA-CCFE-PR(20)23
F. 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…
Preprint Purchase2019
UKAEA-CCFE-PR(19)23
Elina Militello Asp Gerard Corrigan Paula da Silva Aresta Belo Luca Garzotti Derek Harting Florian Köchl Vassili Parail Mario Cavinato Alberto Loarte Michele Romanelli Roberta 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 foll…
Preprint2018
UKAEA-CCFE-PR(18)22
L. Garzotti P. Belo G. Corrigan D. Harting F. Köchl A. Loarte E. Militello Asp V. Parail R.Ambrosino M. Cavinato M. Mattei M. Romanelli R. Sartori M. Valovič
The operation of a tokamak designed to test the sustainability of a thermonuclear grade plasma like the International Tokamak Experimental Reactor (ITER) presents several challenges. Among them is the necessity of fuelling the plasma to reach the density required to generate enough fusion power to achieve Q = 10 and, at the same time, to protect th…
Preprint Published2018
UKAEA-CCFE-PR(18)3
L. Horvath C.F. Maggi F.J. Casson V. Parail L. Frassinetti F. Koechl S. Saarelma M.G. Dunne K.J. Gibson JET Contributors
Recent studies have shown that on JET with the Be/W ITER-like wall (JET-ILW) in high beta discharges with high D2 gas rates the inter-ELM temperature pedestal growth is saturated half way through the ELM cycle, leading to plasmas with reduced confinement, and that the linear MHD stability of these pedestals is inconsistent with the Peeling-Ballooni…
Preprint Published2016
CCFE-PR(16)08
Y. Liu S. Äkäslompolo M. Cavinato F. Koechl T. Kurki-Suonio L. Li V. Parail G. Saibene K. Särkimäki S. Sipilä J. Varje
Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations, produced by ferritic inserts (FIs) and test blanket modules (TBMs), for four ITER plasma scenarios: the 15MA baseline, the 12.5MA hybrid, the 9MA steady state, and the 7.5MA half-field Helium plasma. Due to broad toroidal spectrum of…
Preprint Published2015
CCFE-PR(15)83
J. Varje O. Asunta M. Cavinato M. Gagliardi E. Hirvijoki T. Kurki-Suonio Y. Liu V. Parail G. Saibene S. Sipäl A. Snicker K. Särkimäki S. Äkäslompolo
Mitigating edge localized modes (ELMs) with resonant magnetic perturbations (RMPs) can increase energetic particle losses and resulting wall loads, which have previously been studied in the vacuum approximation. This paper presents recent results of fusion alpha and NBI ion losses in the ITER baseline scenario modelled with the Monte Carlo orbit fo…
Preprint Published2015
CCFE-PR(15)29
M. Romanelli V. Parail P. da Silva Aresta Belo G. Corrigan L. Garzotti D. Harting F. Koechl E. Militello-Asp R. Ambrosino M. Cavinato A. Kukushkin A. Loarte M. Mattei R. Sartori
ITER operations require effective fuelling of the core plasma for conditions in which neutral dynamics through the scrape-off layer (SOL) is expected to affect significantly the efficiency of gas penetration. On the basis of previous analysis for stationary conditions, pellets are foreseen to provide core fuelling of high-Q DT scenarios. In this pa…
Preprint Published2015
CCFE-PR(15)128
V. Parail G. Corrigan P. Da Silva Aresta Belo E. De La Luna D. Harting F. Koechl T. Koskela A. Meigs E. Militello-Asp M. Romanelli M. Tsalas JET-EFDA contributors
The influence of the ITER-like Wall (ILW) with divertor target plate made of tungsten (W), on plasma performance in JET H-mode is being investigated since 2011 (see [1] and references therein). One of the key issues in discharges with low level of D fuelling is observed accumulation of W in the plasma core, which leads to a reduction in plasma perf…
Preprint Published2013
V Parail R Albanese R Ambrosino J-F Artaud K Besseghir M Cavinato G Corrigan J Garcia Et Al
Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration of the operational space and for scenario optimisation. It also provides an assessment of the compatibility of developed scenarios (which include fast transient events) with machine constraints, in particular with the poloidal field (PF) coil system,…
Published2007
P. Mantica G. Corrigan X. Garbet F. Imbeaux J. Lonnroth V. Parail T. Tala A. Taroni M. Valisa H. Weisen
This paper presents an overview of the state of the art of core transport studies in JET. It covers in various sections the topics of heat transport, particle and impurity transport, momentum transport, internal transport barrier physics and integrated core and edge modeling. For each topic, a brief summary of older results obtained under the JET J…
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