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Diagnostics for plasma control : from ITER to DEMO

Authors :
Sean Conroy
Slavomir Entler
F. Janky
Carlo Sozzi
Martin Hron
F. da Silva
W. Treutterer
M. Tardocchi
Alfredo Pironti
Kai Jakob Brunner
H. Meister
Giuseppe Marchiori
I. Duran
J. Kogoj
Lorenzo Figini
F. Maviglia
Wolfgang Biel
C. Finotti
Th. Franke
T. Eade
Marco Cecconello
E. Fable
V. Rohde
Marco Ariola
C. Piron
Inessa Bolshakova
H. Zohm
O. Marchuk
Didier Mazon
M. v. Berkel
N. Rispoli
R. Luis
R. Dux
K. Meyer
M. Z. Tokar
Raffaele Albanese
Massimiliano Mattei
O. Kudlacek
D. Micheletti
A. Malaquias
W. Gonzalez
Göran Ericsson
L. Giacomelli
Andreas Dinklage
Gennady Sergienko
D. Farina
L. Giannone
S. Nowak
R. Cavazzana
A. Kallenbach
S. El Shawish
Anders Hjalmarsson
R. König
Roberto Ambrosino
Analiza M. Silva
Mattia Siccinio
G. De Masi
Biel, W.
Albanese, R.
Ambrosino, R.
Ariola, M.
Berkel, M. V.
Bolshakova, I.
Brunner, K. J.
Cavazzana, R.
Cecconello, M.
Conroy, S.
Dinklage, A.
Duran, I.
Dux, R.
Eade, T.
Entler, S.
Ericsson, G.
Fable, E.
Farina, D.
Figini, L.
Finotti, C.
Franke, T.
Giacomelli, L.
Giannone, L.
Gonzalez, W.
Hjalmarsson, A.
Hron, M.
Janky, F.
Kallenbach, A.
Kogoj, J.
Konig, R.
Kudlacek, O.
Luis, R.
Malaquias, A.
Marchuk, O.
Marchiori, G.
Mattei, M.
Maviglia, F.
De Masi, G.
Mazon, D.
Meister, H.
Meyer, K.
Micheletti, D.
Nowak, S.
Piron, C.
Pironti, A.
Rispoli, N.
Rohde, V.
Sergienko, G.
El Shawish, S.
Siccinio, M.
Silva, A.
da Silva, F.
Sozzi, C.
Tardocchi, M.
Tokar, M.
Treutterer, W.
Zohm, H.
Source :
FUSION ENGINEERING AND DESIGN, Fusion Engineering and Design, 146, 465-472, Fusion engineering and design 146 (2019): 465–472. doi:10.1016/j.fusengdes.2018.12.092, info:cnr-pdr/source/autori:Biel W.; Albanese R.; Ambrosino R.; Ariola M.; Berkel M.V.; Bolshakova I.; Brunner K.J.; Cavazzana R.; Cecconello M.; Conroy S.; Dinklage A.; Duran I.; Dux R.; Eade T.; Entler S.; Ericsson G.; Fable E.; Farina D.; Figini L.; Finotti C.; Franke T.; Giacomelli L.; Giannone L.; Gonzalez W.; Hjalmarsson A.; Hron M.; Janky F.; Kallenbach A.; Kogoj J.; Konig R.; Kudlacek O.; Luis R.; Malaquias A.; Marchuk O.; Marchiori G.; Mattei M.; Maviglia F.; De Masi G.; Mazon D.; Meister H.; Meyer K.; Micheletti D.; Nowak S.; Piron C.; Pironti A.; Rispoli N.; Rohde V.; Sergienko G.; El Shawish S.; Siccinio M.; Silva A.; da Silva F.; Sozzi C.; Tardocchi M.; Tokar M.; Treutterer W.; Zohm H./titolo:Diagnostics for plasma control-From ITER to DEMO/doi:10.1016%2Fj.fusengdes.2018.12.092/rivista:Fusion engineering and design/anno:2019/pagina_da:465/pagina_a:472/intervallo_pagine:465–472/volume:146, Fusion Engineering and Design, Fusion engineering and design 146(Part A), 465-472 (2019). doi:10.1016/j.fusengdes.2018.12.092
Publication Year :
2019

Abstract

The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical and physics limits, while its front-end components will be subject to strong adverse effects within the nuclear and high temperature plasma environment. The ongoing developments for the ITER D&C system represent an important starting point for progressing towards DEMO. Requirements for detailed exploration of physics are however pushing the ITER diagnostic design towards using sophisticated methods and aiming for large spatial coverage and high signal intensities, so that many front-end components have to be mounted in forward positions. In many cases this results in a rapid aging of diagnostic components, so that additional measures like protection shutters, plasma based mirror cleaning or modular approaches for frequent maintenance and exchange are being developed. Under the even stronger fluences of plasma particles, neutron/gamma and radiation loads on DEMO, durable and reliable signals for plasma control can only be obtained by selecting diagnostic methods with regard to their robustness, and retracting vulnerable front-end components into protected locations. Based on this approach, an initial DEMO D&C concept is presented, which covers all major control issues by signals to be derived from at least two different diagnostic methods (risk mitigation).

Details

Language :
English
ISSN :
09203796 and 18737196
Database :
OpenAIRE
Journal :
FUSION ENGINEERING AND DESIGN, Fusion Engineering and Design, 146, 465-472, Fusion engineering and design 146 (2019): 465–472. doi:10.1016/j.fusengdes.2018.12.092, info:cnr-pdr/source/autori:Biel W.; Albanese R.; Ambrosino R.; Ariola M.; Berkel M.V.; Bolshakova I.; Brunner K.J.; Cavazzana R.; Cecconello M.; Conroy S.; Dinklage A.; Duran I.; Dux R.; Eade T.; Entler S.; Ericsson G.; Fable E.; Farina D.; Figini L.; Finotti C.; Franke T.; Giacomelli L.; Giannone L.; Gonzalez W.; Hjalmarsson A.; Hron M.; Janky F.; Kallenbach A.; Kogoj J.; Konig R.; Kudlacek O.; Luis R.; Malaquias A.; Marchuk O.; Marchiori G.; Mattei M.; Maviglia F.; De Masi G.; Mazon D.; Meister H.; Meyer K.; Micheletti D.; Nowak S.; Piron C.; Pironti A.; Rispoli N.; Rohde V.; Sergienko G.; El Shawish S.; Siccinio M.; Silva A.; da Silva F.; Sozzi C.; Tardocchi M.; Tokar M.; Treutterer W.; Zohm H./titolo:Diagnostics for plasma control-From ITER to DEMO/doi:10.1016%2Fj.fusengdes.2018.12.092/rivista:Fusion engineering and design/anno:2019/pagina_da:465/pagina_a:472/intervallo_pagine:465–472/volume:146, Fusion Engineering and Design, Fusion engineering and design 146(Part A), 465-472 (2019). doi:10.1016/j.fusengdes.2018.12.092
Accession number :
edsair.doi.dedup.....57c562a517961b149ddd924815a2ba02