DocumentCode
3171139
Title
Tokamak and RFP ignition requirements
Author
Werley, K.A.
Author_Institution
Los Alamos Nat. Lab., NM, USA
fYear
1991
fDate
30 Sep-3 Oct 1991
Firstpage
416
Abstract
A plasma model is applied to calculate numerically transport-confinement (n τE) requirements and steady-state operation points for both the reversed field pinch (RFP) and tokamak. The CIT tokamak and RFP ignition conditions are examined. Physics differences between RFP and tokamaks and their consequences for a DT ignition machine are discussed. The ignition RFP, compared to a tokamak, has many physics advantages. These advantages, coupled with important engineering advantages translate into significant cost reductions for both ignition and power reactor. The primary drawback of the RFP is the uncertainty that the present confinement scaling will extrapolate to reactor regimes. The 4-MA ZTH was expected to extend the n τE transport scaling data three orders of magnitude above ZT-40 M results, and if the present scaling held, to achieve a DT-equivalent scientific energy breakeven, Q =1. A base-case RFP ignition point is identified with a plasma current of 8.1 MA and no auxiliary heating
Keywords
fusion reactor ignition; fusion reactor theory and design; pinch effect; plasma heating; plasma toroidal confinement; plasma transport processes; CIT; DT; RFP ignition requirements; ZT-40 M; ZTH; auxiliary heating; base-case; confinement scaling; cost reductions; energy breakeven; engineering advantages; plasma current; plasma model; power reactor; steady-state operation points; tokamak; transport scaling; transport-confinement; Heating; Ignition; Impurities; Inductors; Magnetic confinement; Physics; Plasma confinement; Plasma transport processes; Steady-state; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location
San Diego, CA
Print_ISBN
0-7803-0132-3
Type
conf
DOI
10.1109/FUSION.1991.218790
Filename
218790
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