Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: A proliferation resistant fusion breeder for thorium fuel cycle
Sahin, S.; Sarer, B. (Gazi Universitesi, Ankara (Turkey)); Yapici, H.; Sahin, N. (Nigde Universitesi, Aksaray (Turkey))
Abstract
The fissile breeding capability of a (D,T) fusion-fission (hybrid) reactor fueled with thorium is analyzed to provide nuclear fuel for LWRs. Three different fertile material compositions are investigated for fissile fuel breeding:
- ThO2
- ThO2 denaturated with 10% natural-UO2
- ThO2 denaturated with 10% LWR spent fuel.
Two different coolants (pressurized helium and Flibe 'Li2BeF4') are selected for the nuclear heat transfer out of the fissile fuel breeding zone. Depending on the type of the coolant in the fission zone, fusion power plant operation periods between 30 and 48 months are evaluated to achieve a fissile fuel enrichment quality between 3% and 4%, under a first-wall fusion neutron energy load of 5 MW/m2 and a plant factor of 75%. Flibe coolant is superior to helium with regard to fissile fuel breeding. During a plant operation over four years, enrichment grades between 3.0% and 6% are calculated for different fertile fuel and coolant compositions. Fusion breeder with ThO2 produces weapon grade 233U. The denaturation of the 233U fuel is realized with a homogenous mixture of 97% ThO2 with 3% natural-UO2 as well as with 3% LWR spent nuclear fuel. The homogenous mixture of 97% ThO2 with 3% natural-UO2 can successfully denaturate 233U with 238U. However, at the early stages of plant operation, the generated plutonium component is of weapon grade quality. The plutonium component will be denaturated after a plant operation period of 24 and 30 months in Flibe cooled and gas cooled blankets, respectively. On the other hand, the homogenous mixture of 97% ThO2 with 3% LWR spent nuclear fuel remains non-prolific over the entire period for both, uranium and plutonium components. This is an important factor with regard to international safeguarding.
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key words: breeder reactors; breeding blankets; burnup; calculation methods; candu type reactors; fuel management; proliferation; reactor kinetics; safety; thorium cycle; thorium oxides; uranium dioxide; water cooled reactors
- Reference:
- Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--1319, pp:139-153