Showing 1 - 6 of 6 Conference Paper Results
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
2020
UKAEA-CCFE-CP(20)97
22nd Topical Conference on High Temperature Plasma Diagnostics (HTPD), San Diego, USA, 16-19 April 2018
N J Conway A Cackett C F Maggi A G Meigs K-D Zastrow T M Biewer D L Hillis
Since 2010, an in-vessel calibration light source (ICLS) has been used periodically on JET to calibrate a range of diagnostics at UV, visible and IR wavelengths. During shutdowns, the ICLS (essentially an integrating sphere) is positioned within the vacuum vessel by the remote handling (RH) system. Following the 201…
Preprint Published2019
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)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 Purchase2019
UKAEA-CCFE-CP(19)17
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018
K D Lawson M Groth D Harting S Menmuir D Reiter S Brezinsek G Corrigan C F Maggi A G Meigs S Wiesen JET Contributors
Preprint Published
2019
UKAEA-CCFE-CP(19)08
22nd Topical Conference on High Temperature Plasma Diagnostics (HTPD), San Diego, USA, 16-19 April 2018