'Thermal quench' diaporamas de présentation

Report on ITER Design Review Sub-group on : Heat and Particle Loads to in-vessel components associated with limiter and X-point operation, TF ripple, H&CD systems, ELMs, disruptions, VDEs, Marfes and runaway electrons in ITER. Alberto Loarte European Fusion Development Agreement

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Disruption Specification in ARIES

Disruption Specification in ARIES. C. Kessel , PPPL ARIES Project Meeting, January 23-24, 2012, UCSD. Continuing the loading description for PFCs. divertor/heat nominal nominal transient off-normal transient

295 views • 17 slides

TSC time dependent free-boundary simulations of the ACT1 ( aggr phys) plasma and disruptions

TSC time dependent free-boundary simulations of the ACT1 ( aggr phys) plasma and disruptions. C. Kessel , PPPL ARIES Project Meeting, Jan 23-24, 2012, UCSD. ARIES ACT1 (aggr phys) operating point. *the case shown is not the latest, we have done better Ip = 11.25 MA R = 5.5 m a = 1.375 m

103 views • 10 slides

Tokamak disruption (FTU)

Tokamak disruption (FTU). Fusion neutrons. Fus. Neutr. + ? ( >100keV). Photoneutrons. High voltage. Thermal quench. Current quench. Gamma-ray increase during reconnection. Acceleration or just expulsion of pre-existing fast electrons?. Fusion neutrons. Fus. Neutr. + ? ( >100keV).

189 views • 5 slides

Tokamak disruption (FTU)

Tokamak disruption (FTU). Fusion neutrons. Fus. Neutr. + ? ( >100keV). Photoneutrons. High voltage. Thermal quench. Current quench. Gamma-ray increase during reconnection. Acceleration or just expulsion of pre-existing fast electrons?. Fusion neutrons. Fus. Neutr. + ? ( >100keV).

218 views • 5 slides

Modeling of disruption mitigation by massive gas injection (MGI)

115 views • 1 slides