/sup 233/U fusion--fission power system without reprocessing: a preliminary report
- 1 September 1977
- report
- Published by Office of Scientific and Technical Information (OSTI)
Abstract
A preliminary evaluation was made of the technical feasibility of using a fusion reactor to breed /sup 233/U from thorium in high temperature gas cooled fission reactor fuel and of then using this fuel in a fission reactor without reprocessing. Estimates of the neutronic performance of thorium fusion reactor blankets were made. The fuel cycle characteristics of high temperature gas-cooled reactors operating on nonreprocessed fusion-bred /sup 233/U fuel were also estimated. The system performance of symbiotic fusion-fission power systems without reprocessing was then determined.Keywords
This publication has 0 references indexed in Scilit: