Showing 1 - 6 of 6 Conference Paper Results
2020
UKAEA-CCFE-CP(20)123
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021
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
2020
UKAEA-CCFE-CP(20)98
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
C. Giroud N. Aiba F. Militello C. Challis A. Chankin B. Lomanowski D. Hatch J. Harrison D. Frigione D. Moulton S. Pamela F. Parra J. Parisi I. Putzai D. Refy S. Saarelma C. Stavrou B. Tal E. Belonohy S. Brezinsek S. Buller C. Bowman E. Delabie A. Field J. Fontdecaba A. Huber A. Meigs S. Menmuir J. Simpson JET Contributors
Preprint
2019
UKAEA-CCFE-CP(19)48
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
K 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…
Preprint2019
UKAEA-CCFE-CP(19)33
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
C.D. Challis S. Brezinsek I. Coffey N. Hawkes D. Keeling D. King G. Pucella E. Viezzer JET Contributors
The initial Ohmic current ramp phase of JET hybrid plasmas, including a current ‘overshoot’ before the main heating, is used to optimise the q-profile shape to allow access to high β and avoid MHD instabilities [1]. Such hybrid plasmas have never been operated using tritium (T) or mixed deuterium-tritium (D-T) fuel. However, experiments with i…
Preprint Published2019
UKAEA-CCFE-CP(19)20
23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), Princeton, NJ, USA, 17-22 June 2018
S. S. Henderson M. Bernert S. Brezinsek M. Carr M. Cavedon R. Dux D. S. Gahle J. Harrison B. Lipschultz B. Lomanowski A. Meigs M. O’Mullane F. Reimold M. L. Reinke S. Wiesen the EUROfusion MST1 team the ASDEX Upgrade team JET contributors
Reducing the plasma power exhaust impacting on plasma facing components during steady state operation is one of the major design issues in future tokamaks such as ITER. Impurity seeding, e.g. with N, is one method of achieving this and has been used for a long time in tokamak research [1]. In this work we exploit a recently developed spectroscopic …
Preprint Published2019
UKAEA-CCFE-CP(19)17
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018