All Papers - UKAEA Scientific Publications

Showing 1 - 10 of 28 UKAEA Paper Results

UKAEA-CCFE-CP(25)252024

"Global simulations of the exit phase from the flat-top of an ITER 15MA baseline scenario. Fully predictive JINTRAC simulations with consistent treatment of D and T in the whole plasma"
- 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
- V. Parail
- S.D. Pinches
- A.R. Polevoi
- P. Strand
The integrated modelling tool JINTRAC [1] was recently updated and now has the unique capability of fully consistent treatment of Deuterium and Tritium in the whole plasma volume. In this work this is utilized with coupled core-SOL-divertor simulations performed for the ITER 15MA/5.3T DT Q=10 scenario. The work is built on previous simulations publ…
- Preprint
- Published
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(25)2682023

"Assessment of ELMy H-mode operation for ITER Pre-Fusion Power Operation plasmas using JINTRAC"
- E. Tholerus
- L. Garzotti
- V. Parail
- Y. Baranov
- X. Bonnin
- G. Corrigan
- F. Eriksson
- D. Farina
- L. Figini
- D.M. Harting
- S.H. Kim
- F. Koechl
- A. Loarte
- E. Militello Asp
- H. Nordman
- S.D. Pinches
- A.R. Polevoi
- P. Strand
In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure no production of neutrons from fusion reactions. With the expected higher L-H power threshold of hy…
- Preprint
- Published
UKAEA-CCFE-CP(23)612021

"Pedestal particle balance studies in JET-ILW H-mode plasmas"
- L. Horvath
- M. Maslov
- P.A. Schneider
- C.F. Maggi
- L.Frassinetti
- B. Lomanowski
- R.B. Morales
- D. Nina
- S. Saarelma
- J. Simpson
- G. Corrigan
- D.I. Refy
- M.Brix
- T. Pereira
- M. Vecsei
- JET Contributors
The relative role of particle transport and edge fuelling in setting the H-mode density pedestal is still a key open question [1]. Although reduced pedestal models have proven successful in predicting the pedestal pressure for a wide range of plasma scenarios [2,3,4], they lack a first principle based, predictive model for the edge density. Pred…
- Preprint
- Published
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-CP(20)1232020

"Use of the CHEM He II atomic data in JET EDGE2D-EIRENE simulations"
- K D Lawson
- M Groth
- D Harting
- S Menmuir
- 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
- Preprint
- Published
UKAEA-CCFE-CP(20)962020

"Upstream separatrix temperature dependence in EDGE2D-EIRENE for JET H-mode plasmas"
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
- 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

Page 1 of 3Next

UKAEA Papers

Browse our papers below.

"Global simulations of the exit phase from the flat-top of an ITER 15MA baseline scenario. Fully predictive JINTRAC simulations with consistent treatment of D and T in the whole plasma"

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

"Assessment of ELMy H-mode operation for ITER Pre-Fusion Power Operation plasmas using JINTRAC"

"Pedestal particle balance studies in JET-ILW H-mode plasmas"

"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"

"Use of the CHEM He II atomic data in JET EDGE2D-EIRENE simulations"

"Upstream separatrix temperature dependence in EDGE2D-EIRENE for JET H-mode plasmas"

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

UKAEA facilities