All Papers - UKAEA Scientific Publications

Showing 1 - 10 of 19 UKAEA Paper Results

UKAEA-CCFE-PR(24)032024

"Simulations of the stationary Q=10 and the exit phase from the flat-top of an ITER 15MA baseline scenario"
- F.Eriksson
- E.Tholerus
- G.Corrigan
- Y.Baranov
- X.Bonnin
- D.Farina
- L.Figini
- L.Garzotti
- S.H.Kim
- F.Koechl
- A.Loarte
- E.Militello Asp
- C.Olde
- V.Parail
- S.D.Pinches
- A.Polevoi
- P.Strand
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
- Preprint
- Published
UKAEA-CCFE-PR(23)1802023

"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"
- E.R. Solano
- G. Birkenmeier
- C. Silva
- E. Delabie
- J.C. Hillesheim
- A. Baciero
- I. Balboa
- M. Baruzzo
- A. Boboc
- M. Brix
- C. Bourdelle
- I.S. Carvalho
- P. Carvalho
- C.D. Challis
- M. Chernyshova
- A. Chomiczewska
- R. Coelho
- T. Craciunescu
- E. de la Cal
- E. de la Luna
- R. Dumont
- P. Dumortier
- M. Fontana
- J.M. Fontdecaba
- L. Frassinetti
- D. Gallart
- J. Garcia
- C. Giroud
- W. Gromelski
- R.B. Henriques
- J. Hall
- A. Ho
- L. Horvath
- P. Jacquet
- I. Jepu
- E. Joffrin
- A. Kappatou
- P.J. Lomas
- D.L. Keeling
- D.B. King
- E. Kowalska-Strzęciwilk
- M. Lennholm
- E. Lerche
- E. Litherland-Smith
- V.G. Kiptily
- K.K. Kirov
- A. Loarte
- B. Lomanowski
- C.F. Maggi
- J. Mailloux
- M.J. Mantsinen
- M. Maslov
- A.G. Meigs
- I. Monakhov
- R.B. Morales
- A.H. Nielsen
- D. Nina
- C. Noble
- E. Pawelec
- M. Poradzinski
- G. Pucella
- P. Puglia
- D. Réfy
- J.J. Rasmussen
- E. Righi-Steele
- F.G. Rimini
- T. Robinson
- M. Sertoli
- S.A. Silburn
- P. Sirén
- Ž. Štancar
- H.J. Sun
- G. Szepesi
- D. Taylor
- B. Thomas
- E. Tholerus
- G. Verdoolaege
- P. Vincenzi
- B. Viola
- N. Vianello
- T. Wilson
- Preprint
- Published
UKAEA-CCFE-PR(22)572022

"LOCUST-GPU predictions of fast-ion transport and power loads due to ELM-control coils in ITER"
The LOCUST GPU code has been applied to study the fast-ion transport caused by resonant magnetic perturbations in the high-performance Q = 10 ITER baseline scenario. The computational speed of the code is used calculate the impact of the ITER ELM-control-coil system on neutral beam heating efficiency, as well as producing detailed predictions o…
- Preprint
- Published
UKAEA-CCFE-PR(22)332022

"Peripheral temperature gradient screening of high-Z impurities in optimised ‘hybrid’ scenario H-mode plasmas in JET-ILW"
- A R Field
- D Fajardo
- F J Casson
- C Angioni
- C D Challis
- J Hobirk
- A Kappatou
- Hyun-Tae Kim
- E Lerche
- A Loarte
- J Mailloux
- JET Contributors
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the hot edge pedestal of fusion-grade H-mode plasmas has been demonstrated for the first time in the JET-ILW tokamak. Through careful optimisation of the hybrid-scenario, deuterium plasmas with sufficient heating power (≳ 32MW), high enough ion temperature …
- Preprint
UKAEA-CCFE-CP(23)282021

"Scenario development of ITER ELMy H-mode hydrogen plasma"
- E. Tholerus
- L. Garzotti
- Y. Baranov
- G. Corrigan
- F. Eriksson
- D. Farina
- L. Figini
- D.M. Harting
- F. Koechl
- A. Loarte
- E. Militello Asp
- H. Nordman
- V. Parail
- S.D. Pinches
- A.R. Polevoi
- R. Sartori
- P. Strand
An important part of the ITER Research Plan [1] is the Pre-Fusion Power Operation (PFPO) phase, which includes demonstration of H-mode plasma operation and the commissioning of ELM control systems. However, since hydrogen or helium are the main ion species in PFPO plasmas, the L–H power threshold PL–H is expected to be cons…
- Preprint
UKAEA-CCFE-PR(21)772021

"H-mode plasmas in the Pre-Fusion Power Operation 1 phase of the ITER Research Plan"
- 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
- Published
UKAEA-CCFE-PR(21)772021

"H-mode plasmas in the Pre-Fusion Plasma Operation 1 phase of the ITER Research Plan"
- 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 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
- Published
UKAEA-CCFE-PR(20)232019

"Evaluation of fuelling requirements for core density and divertor heat load control in non-stationary phases of the ITER DT 15 MA baseline scenario"
- 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 ad…
- Preprint
- Published
UKAEA-CCFE-CP(19)272019

"Optimisation of ITER 15 MA DT baseline scenario by means of self-consistent fast-converging integrated free-boundary core-edge-SOL IMAS workflow"
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
- Published
UKAEA-CCFE-PR(19)232018

"ITER Fuelling Requirements and Scenario Development for H, He and DT Through JINTRAC Integrated Modelling"
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…
- Preprint
- Published

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UKAEA Papers

Browse our papers below.

"Simulations of the stationary Q=10 and the exit phase from the flat-top of an ITER 15MA baseline scenario"

"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"

"LOCUST-GPU predictions of fast-ion transport and power loads due to ELM-control coils in ITER"

"Peripheral temperature gradient screening of high-Z impurities in optimised ‘hybrid’ scenario H-mode plasmas in JET-ILW"

"Scenario development of ITER ELMy H-mode hydrogen plasma"

"H-mode plasmas in the Pre-Fusion Power Operation 1 phase of the ITER Research Plan"

"H-mode plasmas in the Pre-Fusion Plasma Operation 1 phase of the ITER Research Plan"

"Evaluation of fuelling requirements for core density and divertor heat load control in non-stationary phases of the ITER DT 15 MA baseline scenario"

"Optimisation of ITER 15 MA DT baseline scenario by means of self-consistent fast-converging integrated free-boundary core-edge-SOL IMAS workflow"

"ITER Fuelling Requirements and Scenario Development for H, He and DT Through JINTRAC Integrated Modelling"

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