DocumentCode
3201857
Title
Disruption mitigation technology concepts and implications for ITER
Author
Baylor, L.R. ; Jernigan, T.C. ; Combs, S.K. ; Meitner, S.J. ; Commaux, N. ; Rasmussen, D.A. ; Parks, P.B. ; Glugla, M. ; Maruyama, S. ; Pearce, R.J.H. ; Lehnen, M.
Author_Institution
Oak Ridge Nat. Lab., Oak Ridge, TN, USA
fYear
2009
fDate
1-5 June 2009
Firstpage
1
Lastpage
6
Abstract
Disruptions on ITER present challenges to handle the intense heat flux, the large forces from halo currents, and the potential first wall damage from energetic runaway electrons. Injecting large quantities of material into the plasma during the disruption can reduce the plasma energy and increase its resistivity to mitigate these effects. Assessments of the amount of various mixtures and quantities of material required have been made to provide collision mitigation of runaway electron conversion [1], which is the most difficult challenge. The quantities of material required (~0.5 MPa-m3 for deuterium or helium gas) are large enough to have implications on the design and operation of the vacuum system and tokamak exhaust processing system.
Keywords
Tokamak devices; fusion reactor design; fusion reactor fuel; fusion reactor operation; plasma magnetohydrodynamics; ITER; MHD instabilities; deuterium gas; disruption mitigation technology; electron conversion; fusion reactor design; fusion reactor operation; halo currents; heat flux; helium gas; plasma energy; tokamak exhaust processing system; vacuum system; Collision mitigation; Conductivity; Cryogenics; Deuterium; Electrons; Helium; Plasma density; Plasma materials processing; Thermal quenching; Tokamaks; ITER; disruption; pellet;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location
San Diego, CA
Print_ISBN
978-1-4244-2635-5
Electronic_ISBN
978-1-4244-2636-2
Type
conf
DOI
10.1109/FUSION.2009.5226509
Filename
5226509
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