Zobrazeno 1 - 10
of 765
pro vyhledávání: '"R Kaita"'
Autor:
A. Maan, D.P. Boyle, R. Majeski, S. Banerjee, M. Francisquez, R. Kaita, G.J. Wilkie, W. Capecchi, S. Kubota, C. Hansen, V. Soukhanovskii
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101408- (2023)
A comparison of three sets of Lithium Tokamak Experiment-β (LTX-β) discharges is presented, each with progressively more lithium evaporatively deposited on the stainless steel plasma facing components (PFCs). Multiple observations independently ind
Externí odkaz:
https://doaj.org/article/966b1d6562c948368f1e90557ae689f5
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 161-165 (2019)
Lithium (Li) coating of plasma-facing components (PFC) has led to improved plasma performance in fusion experiments due to the effectiveness of Li in retaining hydrogen (H) isotopes and thus reducing recycling. Since Li readily reacts with background
Externí odkaz:
https://doaj.org/article/3d5a85bcec6344689028cbc130542bb7
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 411-415 (2019)
Conditioning of plasma facing components (PFCs) using lithium (Li) evaporation has shown to improve plasma performance in fusion devices by imposing low recycling boundary conditions. It is important to understand the retention and sputtering dynamic
Externí odkaz:
https://doaj.org/article/dc57f9a59aa94626a0b576d4cc3217ff
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 250-254 (2019)
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak device designed to study lithium plasma facing components (PFCs). The lithium coated wall of LTX has been demonstrated to produce a plasma edge with high electron temperature (200 eV or grea
Externí odkaz:
https://doaj.org/article/710cee5c961045afb92775ad2dfd0471
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 35-40 (2019)
Tokamak plasma facing components have surface roughness that can cause microscopic spatial variations in erosion and deposition and hence influence material migration, erosion lifetime, dust and tritium accumulation, and plasma contamination. However
Externí odkaz:
https://doaj.org/article/ea57eeffd81f4892b6fed0bf1091cc96
Publikováno v:
Nuclear Materials and Energy, Vol 17, Iss , Pp 211-216 (2018)
Boronization is a Plasma Facing Component (PFC) conditioning technique widely used in tokamak machines. The National Spherical Torus Experiment-Upgrade (NSTX-U) applied this conditioning, using a plasma glow with a deuterated Trimethyl-boron (d-TMB)
Externí odkaz:
https://doaj.org/article/af7b55429e7b48cd83f9fdaffe7a385b
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 720-724 (2017)
Operation in the National Spherical Torus Experiment (NSTX) typically used either periodic boronization and inter-shot helium glow discharge cleaning (HeGDC), or inter-shot lithium evaporation without boronization, and initially with inter-shot HeGDC
Externí odkaz:
https://doaj.org/article/7cc58489125248c999e4e697c6f2e065
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 768-773 (2017)
Toroidal asymmetries in divertor carbon and lithium influxes were observed in NSTX, due to toroidal differences in surface composition, tile leading edges, externally-applied three-dimensional (3D) fields and toroidally-localized edge plasma modifica
Externí odkaz:
https://doaj.org/article/2766e0b7b0284d688bb2f5be30b0d76c
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 1248-1252 (2017)
An innovative PFC diagnostic, the Materials Analysis Particle Probe (MAPP) was used to study the chemistry of Plasma Facing Components (PFCs) in the National Spherical Tokamak Experiment Upgrade (NSTX-U). NSTX-U used boronization as conditioning stra
Externí odkaz:
https://doaj.org/article/bda436d155b14138994fc50e985fc31c
Autor:
Santanu Banerjee, D. P. Boyle, A. Maan, R. Majeski, R. Kaita, D. Smith, M. von Hellermann, C. Hansen, W. Capecchi, D. Elliott
Publikováno v:
The Review of scientific instruments. 93(11)
Trapped electron mode (TEM) is the main source of turbulence predicted for the unique operation regime of a flat temperature profile under low-recycling conditions in the LTX-β tokamak, while ion temperature gradient driven turbulence may also occur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::793826fd0fc35807c0a7d6b002a63fc6
https://pubmed.ncbi.nlm.nih.gov/36461475
https://pubmed.ncbi.nlm.nih.gov/36461475