Résumé du preprint DAPNIA-02-04

DAPNIA-02-04
Fusion -- Fission Hybrid System With Molten Salt Blanket for Nuclear Waste Transmutation
E.T.Cheng, R.Plukiene, D.Ridikas
An intensive neutron source is needed for the transmutation process
of nuclear waste. A plasma based fusion device is naturally a
candidate neutron source. In this paper we analyze a typical
molten salt (flibe) blanket, driven by a plasma based fusion
device, dedicated to burn actinides extracted from the LWR spent
fuel. Performance parameters such as k$_{scr}$, burnup, fluxes
and equilibrium conditions were obtained to assess the characteristics
of a flibe based transmutation plant. It seems that nearly 1.1 
metric tons of spent fuel TRU could be burned annually with an   
output of 3~GW$_{th}$  fission power. Detailed burnup calculations
show that equilibrium conditions of the fuel concentration in
the flibe transmutation blanket could be achieved, provided that
fission products were removed at least in part and fresh spent
fuel TRU was added during burnup on-line.

 

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