Zobrazeno 1 - 10
of 100
pro vyhledávání: '"L. Savoldi Richard"'
Autor:
Antonio Froio, Roberto Zanino, L. Savoldi Richard, Roberto Bonifetto, Stefano Carli, Arnaud Foussat
Publikováno v:
Cryogenics. 63:231-240
Artificial Neural Networks (ANNs) are applied to the development of a simplified transient model of the ITER Central Solenoid (CS), aiming at predicting the evolution of the pulsed heat load from the CS to the LHe bath during plasma operation. The AN
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ae3c9678f1d0e2266ff11d2177d11b3d
https://doi.org/10.1016/j.cryogenics.2014.03.003
https://doi.org/10.1016/j.cryogenics.2014.03.003
Autor:
J. Izquierdo, Roberto Zanino, L. Savoldi Richard, Sabrina Corpino, Y. Utin, R. Le Barbier, Fabio Subba
Publikováno v:
Fusion Engineering and Design. 88:3248-3262
The 3D Computational Fluid Dynamic (CFD) steady state analysis of the regular sector #5 of the ITER vacuum vessel (VV) is presented in these two companion papers using the commercial software ANSYS-FLUENT®. The pure hydraulic analysis, concentrating
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ba0b993fd3a64e8a1a138cbf574068e8
https://doi.org/10.1016/j.fusengdes.2013.10.005
https://doi.org/10.1016/j.fusengdes.2013.10.005
Publikováno v:
Cryogenics. 57:173-180
The pulsed heat load to the cryoplant is an important issue in the design and operation of tokamaks adopting superconducting (SC) magnets for the magnetic confinement, as the International Thermonuclear Experimental Reactor (ITER). The smoothing of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::13de86fd776af26054e18a4c398aa73d
https://doi.org/10.1016/j.cryogenics.2013.07.005
https://doi.org/10.1016/j.cryogenics.2013.07.005
Publikováno v:
Cryogenics. 57:31-44
Large variations of the heat load coming from the superconducting magnets to the cryoplant in a tokamak are an undesired consequence of the intrinsically pulsed operation of the machine. In this paper, the cryogenic circuit module of the 4C (Cryogeni
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7936c7fee344e3cf318b485fbcba4d79
https://doi.org/10.1016/j.cryogenics.2013.04.005
https://doi.org/10.1016/j.cryogenics.2013.04.005
Publikováno v:
Nuclear Engineering and Design. 261:85-94
A new multi-physics simulation tool – FRENETIC (Fast REactor NEutronics/Thermal-hydraulICs) – is presented for the quasi-3D analysis of a lead-cooled fast reactor core with the hexagonal fuel element configuration, as currently proposed within th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fc27f58f319c4254f410b4ab75c117bb
https://doi.org/10.1016/j.nucengdes.2013.03.030
https://doi.org/10.1016/j.nucengdes.2013.03.030
Publikováno v:
IEEE Transactions on Plasma Science. 40:710-714
KSTAR is a fully superconducting tokamak, in operation since 2008 at the National Fusion Research Institute in Korea. All coils are wound using cable-in-conduit conductors and cooled with forced-flow supercritical helium (SHe) at 4.5 K and 5.5 bar. W
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5ea393495dc9b248af5c0afb7ba67d3b
https://doi.org/10.1109/tps.2011.2181874
https://doi.org/10.1109/tps.2011.2181874
Publikováno v:
IEEE Transactions on Plasma Science. 40:782-787
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at the Karlsruhe Institute of Technology, Germany, up to a maximum transport current of 80 kA and a peak magnetic field of ~ 10 T. Here, we apply the 4C c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fd3cbf602451ef391cd9536b65ea5654
https://doi.org/10.1109/tps.2012.2184839
https://doi.org/10.1109/tps.2012.2184839
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, v.86, 1549-1552 (2011)
Fusion Engineering and Design, v.86, 1549-1552 (2011)
The recently developed 4C thermal-hydraulic code is validated here against experimental data from the cool-down of a non-planar coil of the Wendelstein 7-X stellarator from room temperature to the superconducting transition temperature of ∼10 K, pe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ad19e2a3b073699c1961af942c7bd7fb
https://doi.org/10.1016/j.fusengdes.2010.12.070
https://doi.org/10.1016/j.fusengdes.2010.12.070
Publikováno v:
Cryogenics. 50:158-166
Dual-channel cable-in-conduit conductors (CICC) are used in the superconducting magnets for the International Thermonuclear Experimental Reactor (ITER). As the CICC axial/transverse size ratio is typically ∼1000, 1D axial models are customarily use
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::36e30d292b0f56ea983bb21625f5017f
https://doi.org/10.1016/j.cryogenics.2009.11.005
https://doi.org/10.1016/j.cryogenics.2009.11.005
Publikováno v:
Fusion Engineering and Design. 82:1607-1613
We present a new multi-solid multi-channel (M 3 ) thermal–hydraulic model for the analysis of the International Thermonuclear Experimental Reactor (ITER) Cable-In-Conduit Conductors (CICC). The model discretizes the cross section of an ITER CICC in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1852e7cd1099ae92f8ec1f28900bc45a
https://doi.org/10.1016/j.fusengdes.2007.04.035
https://doi.org/10.1016/j.fusengdes.2007.04.035