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Diagnostics for plasma control -: From ITER to DEMO
Forschungszentrum Julich, Inst Energie & Klimaforschurg, Julich, Germany;Univ Ghent, Dept Appl Phys, Ghent, Belgium.
Univ Napoli Federico II, Consorzio CREATE, Naples, Italy.
Univ Napoli Parthenope, Consorzio CREATE, Naples, Italy.
Univ Napoli Parthenope, Consorzio CREATE, Naples, Italy.
Vise andre og tillknytning
2019 (engelsk)Inngår i: Fusion engineering and design, ISSN 0920-3796, E-ISSN 1873-7196, Vol. 146, nr A, s. 465-472Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

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).

sted, utgiver, år, opplag, sider
ELSEVIER SCIENCE SA , 2019. Vol. 146, nr A, s. 465-472
Emneord [en]
ITER, DEMO, Tokamak, Plasma control, Plasma diagnostics
HSV kategori
Identifikatorer
URN: urn:nbn:se:uu:diva-396638DOI: 10.1016/j.fusengdes.2018.12.092ISI: 000488307400104OAI: oai:DiVA.org:uu-396638DiVA, id: diva2:1368603
Konferanse
30th Symposium on Fusion Technology (SOFT), SEP 16-21, 2018, Messina, ITALY
Tilgjengelig fra: 2019-11-07 Laget: 2019-11-07 Sist oppdatert: 2019-11-07bibliografisk kontrollert

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