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Epithermal-Thermal Pu-Th and 233U-U Reactor Systems

Alex Galperin, Yigal Ronen

Nuclear Technology / Volume 58 / Number 3 / September 1982 / Pages 388-396

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A32974

Received November 3, 1981 Accepted for Publication March 22, 1982 A symbiotic system of Pu-Th- and 233U-U-fueled reactors has been proposed and analyzed. The Pu-Th reactors utilize a tight lattice core and the 233U-U reactors utilize a regular pressurized water reactor (PWR) core. The two cases were investigated with different Pu-Th cores (system A: VM/VF =0.4 and system B: VM/VF - 1.0) and similar 233U-U cores. The cumulative 30-yr requirements of uranium ore and separative work for both systems were evaluated and indicated significant savings compared to current PWRs with plutonium recycle and the cross-progeny fuel cycle. The fuel cycle costs calculated for the proposed systems were slightly higher than those for the current PWR cycle.