Reactor Physics and Fuel-Cycle Analyses
- 1 February 1970
- journal article
- research article
- Published by Taylor & Francis in Nuclear Applications and Technology
- Vol. 8 (2) , 208-219
- https://doi.org/10.13182/nt70-a28626
Abstract
As presently conceived at Oak Ridge National Laboratory and described in this issue, the single-fluid Molten-Salt Breeder Reactor, operating on the 232Th-233 U fuel cycle and based on a reference design, has a breeding ratio of ~1.06, specific fissile inventory of 1.5 kg/MW(e), a fuel doubling time of ~20 years, and fuel cycle costs of ~0.7 mill/kWh(e). Start-up may be accomplished with either enriched uranium or plutonium, with little effect on fuel cost; the breeding ratio, averaged over reactor life, is reduced 0.01 to 0.02 relative to the equilibrium cycle. Operated as a converter, with limited chemical processing, the reactor may have a conversion ratio in the range 0.8 to 0.9 with fuel cycle costs of 0.7 to 0.9 mill/kWh(e).Keywords
This publication has 4 references indexed in Scilit:
- Molten-Salt Reactor ChemistryNuclear Applications and Technology, 1970
- The Design and Performance Features of a Single-Fluid Molten-Salt Breeder ReactorNuclear Applications and Technology, 1970
- Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor DesignNuclear Applications and Technology, 1970
- Engineering Development of the MSBR Fuel RecycleNuclear Applications and Technology, 1970