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Diagnostics for plasma control : from ITER to DEMO
- 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).
- Subjects :
- Tokamak
Materials science
Plasma diagnostic
ComputingMethodologies_SIMULATIONANDMODELING
Nuclear engineering
ComputerApplications_COMPUTERSINOTHERSYSTEMS
01 natural sciences
010305 fluids & plasmas
law.invention
Plasma diagnostics
HALL SENSORS
Fusion, plasma och rymdfysik
DESIGN
law
ITER
0103 physical sciences
Medicine and Health Sciences
ddc:530
General Materials Science
010306 general physics
DEMO
Civil and Structural Engineering
ISSUES
Mechanical Engineering
RESEARCH-AND-DEVELOPMENT
DENSITY-MEASUREMENTS
Plasma
Fusion power
Plasma control
Fusion, Plasma and Space Physics
Nuclear Energy and Engineering
EDGE
Hall effect sensor
ELECTRON
INTEGRATION
SYSTEM
Subjects
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