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Epithermal-thermal Pu-Th and /sup 233/U-U reactor systems

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6026567

A symbiotic system of Pu-Th- and /sup 233/U-U-fueled reactors has been proposed and analyzed. The Pu-Th reactors utilize a tight lattice core and the /sup 233/U-U reactors utilize a regular pressurized water reactor (PWR) core. The two cases were investigated with different Pu-Th cores (system A: V /SUB m/ /V /SUB f/ = 0.4 and system B: V /SUB m/ /V /SUB f/ = 1.0) and similar /sup 233/U-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.

Research Organization:
Ben-Gurion University of the Negev, Department of Nuclear Engineering, Beer Sheva
OSTI ID:
6026567
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 58:3; ISSN NUTYB
Country of Publication:
United States
Language:
English