Mirrors for ITER Optical Diagnostics
Creators
- Razdobarin, A.1
- Mukhin, E.1
- Semenov, V.1
- Tolstyakov, S.1
- Kochergin, M.1
- Kurskiev, G.1
- Berezutsky, A.1
- Kirilenko, D.1
- Sitnikova, A.1
- Masyukevich, S.1
- Chernakov, P.1
- Voitsenya, V.2
- Bondarenko, V.2
- Konovalov, V.2
- Ryzhkov, I.2
- Skorik, O.2
- Gorodetsky, A.3
- Bukhovets, V.3
- Zalavutdinov, R.3
- Zakharov, A.3
- Arkhipov, I.3
- Smirnov, A.4
- Chernoiziumskaya, T.4
- Khilkevitch, E.4
- Vukolov, K.5
- Orlovskiy, I.5
- Alekseev, A.5
- Andrew, P.6
- 1. Ioffe Physical Technical Institute of the Russian Academy of Sciences, St. Petersburg (Russian Federation)
- 2. National Science Centre, Kharkov Institute of Physics and Technology, Kharkov (Ukraine)
- 3. Frumkin Institute of Physical Chemistry and Electrochemistry, Moscow (Russian Federation)
- 4. Saint-Petersburg State Polytechnic University, St. Petersburg (Russian Federation)
- 5. National Research Centre 'Kurchatov Institute', Moscow (Russian Federation)
- 6. ITER Organization, Saint Paul Lez Durance (France)
Description
Full text: The large distance between ITER vacuum windows and the plasma boundary necessitates the use of in-vessel optical diagnostic components. High particle fluxes, temperature and radiation level expected inside ITER imposes considerable limitations on mirrors design. The choice of FM (First Mirrors) structure and material depends on the mirror location and on the diagnostic needs. The presentation covers the most general approaches to the FM problem in ITER and demonstrates the implantation of basic concepts in the design of FM in the divertor Thomson scattering system. The FM design options and their advantages and disadvantages in different operation conditions expected in ITER are discussed along with new results on the development of optics cleaning and deposition-mitigating techniques. The focus is on the efficiency of plasma cleaning combined with blowing out contaminations. The impact of plasma treatment on the mirror surface is also discussed. The parameters of cleaning capacitively-coupled discharge in working ITER gas — deuterium were calculated within the hydrodynamic model and experimentally verified. The blowing-out efficiency has been estimated for the prototype of the divertor laser launcher duct. The implementation of other protection and cleaning techniques, like laser cleaning, heating and shutters is considered. (author)
Additional details
Publishing Information
- Imprint Title
- 24. IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 789 p.
- Journal Page Range
- p. 626
- Report number
- IAEA-CN--197
Conference
- Title
- 24. IAEA Fusion Energy Conference
- Acronym
- FEC 2012
- Dates
- 8-13 Oct 2012
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45034045
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLEANING; CONTAMINATION; DESIGN; DEUTERIUM; DIVERTORS; EFFICIENCY; HYDRODYNAMIC MODEL; ITER TOKAMAK; LASERS; MIRRORS; PLASMA; SURFACES; THOMSON SCATTERING
- Descriptors DEC
- CLOSED PLASMA DEVICES; HYDROGEN ISOTOPES; INELASTIC SCATTERING; ISOTOPES; LIGHT NUCLEI; MATHEMATICAL MODELS; NUCLEI; ODD-ODD NUCLEI; PARTICLE MODELS; SCATTERING; STABLE ISOTOPES; STATISTICAL MODELS; THERMODYNAMIC MODEL; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Secondary number(s)
- ITR/P5--34