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| Fältnamn | Indikatorer | Metadata |
|---|---|---|
| 000 | 03614naa a2200625 4500 | |
| 001 | oai:DiVA.org:kth-131235 | |
| 003 | SwePub | |
| 008 | 131010s2013 | |||||||||||000 ||eng| | |
| 024 | 7 | a https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-1312352 URI |
| 024 | 7 | a https://doi.org/10.1088/0029-5515/53/9/0930022 DOI |
| 040 | a (SwePub)kth | |
| 041 | a engb eng | |
| 042 | 9 SwePub | |
| 072 | 7 | a ref2 swepub-contenttype |
| 072 | 7 | a art2 swepub-publicationtype |
| 100 | 1 | a Philipps, V.4 aut |
| 245 | 1 0 | a Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices |
| 264 | c 2013-08-08 | |
| 264 | 1 | b IOP Publishing,c 2013 |
| 338 | a print2 rdacarrier | |
| 500 | a QC 20131011 | |
| 520 | a Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D-T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle. This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region. | |
| 650 | 7 | a NATURVETENSKAPx Fysik0 (SwePub)1032 hsv//swe |
| 650 | 7 | a NATURAL SCIENCESx Physical Sciences0 (SwePub)1032 hsv//eng |
| 653 | a Induced Breakdown Spectroscopy | |
| 653 | a Diagnostics | |
| 653 | a Components | |
| 653 | a Retention | |
| 700 | 1 | a Malaquias, A.4 aut |
| 700 | 1 | a Hakola, A.4 aut |
| 700 | 1 | a Karhunen, J.4 aut |
| 700 | 1 | a Maddaluno, G.4 aut |
| 700 | 1 | a Almaviva, S.4 aut |
| 700 | 1 | a Caneve, L.4 aut |
| 700 | 1 | a Colao, F.4 aut |
| 700 | 1 | a Fortuna, E.4 aut |
| 700 | 1 | a Gasior, P.4 aut |
| 700 | 1 | a Kubkowska, M.4 aut |
| 700 | 1 | a Czarnecka, A.4 aut |
| 700 | 1 | a Laan, M.4 aut |
| 700 | 1 | a Lissovski, A.4 aut |
| 700 | 1 | a Paris, P.4 aut |
| 700 | 1 | a van der Meiden, H. J.4 aut |
| 700 | 1 | a Petersson, Peru KTH,Fusionsplasmafysik4 aut0 (Swepub:kth)u1mnanst |
| 700 | 1 | a Rubel, Mareku KTH,Fusionsplasmafysik4 aut0 (Swepub:kth)u1vrej8y |
| 700 | 1 | a Huber, A.4 aut |
| 700 | 1 | a Zlobinski, M.4 aut |
| 700 | 1 | a Schweer, B.4 aut |
| 700 | 1 | a Gierse, N.4 aut |
| 700 | 1 | a Xiao, Q.4 aut |
| 700 | 1 | a Sergienko, G.4 aut |
| 710 | 2 | a KTHb Fusionsplasmafysik4 org |
| 773 | 0 | t Nuclear Fusiond : IOP Publishingg 53:9, s. 093002-q 53:9<093002-x 0029-5515x 1741-4326 |
| 856 | 4 8 | u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-131235 |
| 856 | 4 8 | u https://doi.org/10.1088/0029-5515/53/9/093002 |
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