DocumentCode
2153857
Title
Disruption design criteria for JET in-vessel components
Author
Riccardo, V. ; Andrew, P. ; Kaye, A. ; Noll, P.
Author_Institution
UKAEA/Euratom Assoc., UK
fYear
2002
fDate
2002
Firstpage
384
Lastpage
387
Abstract
In view of the substantial modification in the JET plasma facing components foreseen for the 2004 shutdown, the design criteria for in-vessel components have been updated building up on the operational experience with divertor plasmas gained since the early ´90s. Typically the most demanding design loads occur during disruptions and vertical displacement events (VDEs). In fast disruptions (e.g. density limit driven) the largest contribution to the loads comes from currents induced by fast change of the poloidal field, which tends to be proportional to the plasma current decay rate, the maximum of which has been observed to be linear with the pre-disruption plasma current. This implies that in the fastest events the current quench has a fixed duration at JET, about 10 ms. Usually VDEs take place on a longer time scale, and therefore halo currents determine the worst loading condition in these cases. Analysis of recent VDE data confirmed the previously observed magnitude of asymmetries: the toroidal peaking factor (TPF) up to 1.8 in upward VDEs and up to 1.4 in downward VDEs; the ratio average poloidal halo to initial plasma current (f) up to 23% in upward VDEs and up to 30% in downward VDEs. Experimental evidence to justify the new criteria and recipes on how to apply them to JET are included. The data used for the revision of the design criteria are discussed and compared with the assumptions used in the design of the components already present in the JET vacuum vessel.
Keywords
Tokamak devices; fusion reactor design; fusion reactor divertors; fusion reactor safety; nuclear engineering computing; plasma toroidal confinement; plasma transport processes; vacuum apparatus; 10 ms; JET in-vessel components; VDE data; density limit driven; disruption design criteria; divertor plasmas; halo currents; operational experience; plasma current decay rate; plasma facing components; poloidal field; toroidal peaking factor; vacuum vessel; vertical displacement events; Current measurement; Displacement measurement; Force measurement; Guidelines; Helium; Phase measurement; Plasma density; Plasma sources; Q measurement; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2002. 19th Symposium on
Print_ISBN
0-7803-7073-2
Type
conf
DOI
10.1109/FUSION.2002.1027718
Filename
1027718
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