Commissioning and First Results of the OLMAT facility

dc.contributor.authorTabares, F.L.
dc.contributor.authorOyarzabal, E.
dc.contributor.authorAlegre, D.
dc.contributor.authorTafalla, D.
dc.contributor.authorMcCarthy, K.J.
dc.contributor.authorde Castro, A.
dc.contributor.authorAscasíbar, E.
dc.contributor.authorSoleto, A.
dc.contributor.authorFernandez-Berceruelo, I.
dc.contributor.authorCarrasco, R.
dc.contributor.authorMartin, F.
dc.contributor.authorSebastian, J.A.
dc.contributor.authorGomez-manchon, J.
dc.contributor.authorPereira, A.
dc.contributor.authorde la Peña, A.
dc.date.accessioned2024-02-16T15:56:09Z
dc.date.available2024-02-16T15:56:09Z
dc.date.issued2023-02-01
dc.description.abstractThe 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 conditiones_ES
dc.description.sponsorshipThis 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) 113373es_ES
dc.identifier.issn0920-3796
dc.identifier.urihttps://hdl.handle.net/20.500.14855/2637
dc.language.isoenges_ES
dc.publisherFusion Engineering and Designes_ES
dc.relation.ispartofseries187;113373
dc.rights.accessRightsopen accesses_ES
dc.subjectHHF facilitieses_ES
dc.subjecttarget materialses_ES
dc.subjectliquid metalses_ES
dc.subjectDEMOes_ES
dc.subjectITERes_ES
dc.subjectCPSes_ES
dc.subjectOLMATes_ES
dc.subjectvapor shieldinges_ES
dc.titleCommissioning and First Results of the OLMAT facilityes_ES
dc.typejournal articlees_ES

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