FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4

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Gazi University Journal of Science
Volume:16 Issue:2
FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4

FISSILE FUEL BREEDING IN THE ARIES-ST FUSION REACTOR BY USING MOLTEN SALT WITH UF4

Authors : Mustafa ÜBEYLİ

Pages : 387-394

View : 21 | Download : 9

Publication Date : 2010-08-06

Article Type : Other Papers

Abstract :ABSTRACT Fissile fuel breeding in the ARIES-ST of the 1000 MW el power plant is investigated by using molten salt containing UF 4 Calculations are done with the aid of one-dimensional code of SCALE4.3. In this hybrid model, a substantial amount of fissile fuel can be produced with a fissile fuel breeding ratio of 239 Pu = 0.115 per incident neutron at start-up conditions, that corresponds to 3558 kg 239 Pu/year by a full fusion power of 2740 MW. Tritium breeding ratio is found as 1.14 so that tritium self-sufficiency is maintained for DT fusion driver. Key Words: ARIES-ST fusion reactor, molten salt, fissile fuel breeding.
Keywords : ARIES ST fusion reactor, molten salt, fissile fuel breeding

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