FUSION BREEDER WITH ENHANCED SAFEGUARDING CAPABILITIES AGAINST NUCLEAR-WEAPON PROLIFERATION

The breeding capability of a fusion reactor for Pu-239 is analyzed to provide fissile fuel for LWRs as a prospective alternative in addition to existing methods of nuclear fuel enrichment, such as gas diffusion and gas centrifuge plants. The analysis is conducted for the catalyze d-(D,D) and (D,T) fusion reactors. Two different coolants (helium gas and Flibe ''Li2BeF4'') are selected for the nuclear heat transfer out of the fissile breeding zone fuelled with natural uranium. Depending o n the type of fusion driver and coolant in the fission zone, power pla nt operation periods between 12 and 36 months are evaluated to achieve a fissile fuel enrichment quality between 3% and 4% under a first-wal l fusion neutron energy load of 5 MW/m(2) and a plant factor of 75%. F or unit fusion neutron energy flux on the first-wall, a catalyzed (D,D ) fusion reactor can breed faster than a (D,T) reactor because the for mer is richer in neutrons than the latter. The Flibe coolant is superi or to helium coolant with regard to fissile fuel breeding. During a pl ant operation over four years, enrichment grades between 4.4% and 8.9% are calculated. The denaturation of the plutonium fuel requires about 2 years of irradiation with fusion neutrons for all investigated case s. During this period, it is possible to breed a high quality, but den atured plutonium for light water reactors. This is an important factor with regard to international safeguarding. (C) 1998 Elsevier Science Ltd. All rights reserved.