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research article

Divertor currents optimization procedure for JET-ILW high flux expansion experiments

Calabro, G.
•
Maviglia, F.
•
Minucci, S.
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April 1, 2018
Fusion Engineering And Design

This paper deals with a divertor coil currents optimized procedure to design High Flux Expansion (HFE) configurations in the JET tokamak aimed to study the effects of flux expansion variation on the radiation fraction and radiated power re-distribution. A number of benefits of HFE configuration have been experimentally demonstrated on TCV, EAST, NSTX and DIII-D tokamaks and are under investigation for next generation devices, as DEMO and DTT. The procedure proposed here exploits the linearized relation between the plasma-wall gaps and the Poloidal Field (PF) coil currents. Once the linearized model is provided by means of CREATE-NL code, the divertor coils currents are calculated using a constrained quadratic programming optimization procedure, in order to achieve HFE configuration. Flux expanded configurations have been experimentally realized both in ohmic and heated plasma with and without nitrogen seeding. Preliminary results on the effects of the flux expansion variation on total power radiation increase will be also briefly discussed.

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Type
research article
DOI
10.1016/j.fusengdes.2018.02.041
Web of Science ID

WOS:000431094100018

Author(s)
Calabro, G.
Maviglia, F.
Minucci, S.
Viola, B.
Abduallev, S.
Abhangi, M.
Abreu, P.
Afzal, M.
Aggarwal, K. M.
Ahlgren, T.
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Date Issued

2018-04-01

Published in
Fusion Engineering And Design
Volume

129

Start page

115

End page

119

Subjects

Nuclear Science & Technology

•

advanced configuration

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quadratic programming optimization

•

flux expansion

•

scrape-off layer

•

detachment

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
SPC  
Available on Infoscience
September 20, 2019
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/161373
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