Status of the R&D activities to the design of an ITER core CXRS diagnostic system
Creators
- 1. Institute of Energy and Climate Research IEK-4 (Plasma Physics), Forschungszentrum Jülich (FZJ), Trilateral Euregio Cluster, D-52425 Jülich (Germany)
- 2. Wigner Research Centre for Physics (Wigner RCP), HU-1121 Budapest (Hungary)
- 3. Culham Centre for Fusion Energy (CCFE), Culham OX14 3DB (United Kingdom)
- 4. Eindhoven University of Technology (TU/e), PO Box 513, NL-5600 MB Eindhoven (Netherlands)
- 5. Zentralinstitut für Engineering, Elektronik und Analytik ZEA-1 (Engineering and Technology), FZJ, Trilateral Euregio Cluster, D-52425 Jülich (Germany)
Description
Highlights: • The CXRS diagnostic for the core plasma of ITER will provide observation of the dedicated diagnostic beam (DNB) over a wide radial range, roughly r/a = 0.7 to 0. • A high performance (étendue × transmission, dynamic range) is expected for the port plug system since the beam attenuation is large and the background light omnipresent. • The design is particularly challenging in view of the ITER environment, especially with respect to the first mirror which faces the plasma. • The current status of development is presented by detailing several sub-systems before a four years design phase under an FPA between F4E and the ITER core CXRS Consortium (IC3). - Abstract: The CXRS (Charge-eXchange Recombination Spectroscopy) diagnostic for the core plasma of ITER will be designed to provide observation of the dedicated diagnostic beam (DNB) over a wide radial range, roughly from a normalised radius r/a = 0.7 to close to the plasma axis. The collected light will be transported through the Upper Port Plug #3 (UPP3) to a bundle of fibres and ultimately to a set of remote spectrometers. The design is particularly challenging in view of the ITER environment of particle, heat and neutron fluxes, temperature cycles, electromagnetic loads, vibrations, expected material degradation and fatigue, constraints against tritium penetration, integration in the plug and limited opportunities for maintenance. Moreover, a high performance (étendue × transmission, dynamic range) is expected for the port plug system since the beam attenuation is large and the background light omnipresent, especially in terms of bremsstrahlung, line radiation and reflections. The present contribution will give an overview of the current status and activities which deal with the core CXRS system, summarising the investigations which have taken place before entering the actual development and design phase.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.05.039Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.05.039;
- PII
- S0920-3796(15)30002-8;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 96-97
- Journal Page Range
- p. 129-135
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 28. symposium on fusion technology
- Acronym
- SOFT-28
- Dates
- 29 Sep - 3 Oct 2014
- Place
- San Sebastian (Spain)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48006353
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATTENUATION; BEAMS; BREMSSTRAHLUNG; CHARGE EXCHANGE; DESIGN; HEAT FLUX; ITER TOKAMAK; LIMITING VALUES; MIRRORS; NEUTRON FLUX; PLASMA; RECOMBINATION; REFLECTION; SPECTROMETERS; SPECTROSCOPY; TRITIUM; VISIBLE RADIATION
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELECTROMAGNETIC RADIATION; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MEASURING INSTRUMENTS; NUCLEI; ODD-EVEN NUCLEI; RADIATION FLUX; RADIATIONS; RADIOISOTOPES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.