Commissioning and First Results of the OLMAT facility
| dc.contributor.author | Tabares, F.L. | |
| dc.contributor.author | Oyarzabal, E. | |
| dc.contributor.author | Alegre, D. | |
| dc.contributor.author | Tafalla, D. | |
| dc.contributor.author | McCarthy, K.J. | |
| dc.contributor.author | de Castro, A. | |
| dc.contributor.author | Ascasíbar, E. | |
| dc.contributor.author | Soleto, A. | |
| dc.contributor.author | Fernandez-Berceruelo, I. | |
| dc.contributor.author | Carrasco, R. | |
| dc.contributor.author | Martin, F. | |
| dc.contributor.author | Sebastian, J.A. | |
| dc.contributor.author | Gomez-manchon, J. | |
| dc.contributor.author | Pereira, A. | |
| dc.contributor.author | de la Peña, A. | |
| dc.date.accessioned | 2024-02-16T15:56:09Z | |
| dc.date.available | 2024-02-16T15:56:09Z | |
| dc.date.issued | 2023-02-01 | |
| dc.description.abstract | The OLMAT (Optimization of Liquid Metal Advanced Targets) facility has recently undergone the commissioning and start-up phases. Solid Titanium-Zirconium- Molybdenum (TZM) alloy and liquid tin (Sn) metallic targets were exposed to a hydrogen neutral beam injector (NBI) particle flux with power densities up to 58 ±14 MW/m2, pulse duration up to 150 ms, and repetition rates up to 2 pulses/minute. These beam parameters are well above the estimates based on the typical performance of this NBI system when used for heating plasmas in the TJ-II stellarator. The parameters of the plasma generated through the interaction of the fast (32.5 keV) neutrals and ions and the solid were characterized by spectroscopic methods while surface temperature and total absorbed power were followed using pyrometry, infrared (IR) thermography, and calorimetry, respectively. Targets were visually monitored during the exposure and microscopically analyzed ex-situ. Electrical isolation of the target permitted recording the floating voltage during irradiation as well as for active biasing tests. In this work, a description of the facility, its operating parameters, and firsts results are provided and assessed as a new High Heat Flux (HHF) Facility for testing solid and liquid metal divertor targets under reactor-relevant heat load condition | es_ES |
| dc.description.sponsorship | This work was partially financed by the Spanish ‘Ministry of Science and Innovation’ under projects ENE2014-58918-R, RTI2018-096967-B-I00 and PID2020-116599RB-I00. This work has been carried out within the framework of the Eurofusion Consortium and has received funding from the Euratom research and training program 2014–2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The authors are indebted to Dr Macarena Liniers and Dr Angel Perea for their contribution to the thermal model calculations and discussion. | es_ES |
| dc.identifier.citation | [1] F.L. Tabarés et al., Fusion Engineering and Design 187 (2023) 113373 | es_ES |
| dc.identifier.issn | 0920-3796 | |
| dc.identifier.uri | https://hdl.handle.net/20.500.14855/2637 | |
| dc.language.iso | eng | es_ES |
| dc.publisher | Fusion Engineering and Design | es_ES |
| dc.relation.ispartofseries | 187;113373 | |
| dc.rights.accessRights | open access | es_ES |
| dc.subject | HHF facilities | es_ES |
| dc.subject | target materials | es_ES |
| dc.subject | liquid metals | es_ES |
| dc.subject | DEMO | es_ES |
| dc.subject | ITER | es_ES |
| dc.subject | CPS | es_ES |
| dc.subject | OLMAT | es_ES |
| dc.subject | vapor shielding | es_ES |
| dc.title | Commissioning and First Results of the OLMAT facility | es_ES |
| dc.type | journal article | es_ES |
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