Development of small, fast reactor core designs using lead-based coolant

Conference · Wed Sep 15 00:00:00 EDT 1999

OSTI ID:23142175

Hill, R. N.; Cahalan, J. E.; Khalil, H. S.; Wade, D. C. ^[1]

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1. Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

A variety of small (100 MWe) fast reactor core designs are developed; these include compact configurations, long-lived (15-year fuel lifetime) cores, and derated, natural circulation designs. Trade studies are described which identify key core design issues for lead-based coolant systems. Performance parameters and reactivity feedback coefficients are compared for lead-bismuth eutectic (LBE) and sodium-cooled cores of consistent design. The results of these studies indicate that the superior neutron reflection capability of lead alloys reduces the enrichment and burnup swing compared to conventional sodium-cooled systems; however, the discharge fluence is significantly increased. The size requirement for long-lived systems is constrained by reactivity loss considerations, not fuel burnup or fluence limits. The derated lead-alloy cooled natural circulation cores require a core volume roughly eight times greater than conventional compact systems. In general, reactivity coefficients important for passive safety performance are less favorable for the larger, derated configurations.

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23142175
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BURNUP
COOLANTS
COOLING SYSTEMS
FAST REACTORS
ISOTOPE SEPARATION
LEAD-BISMUTH EUTECTIC
NATURAL CONVECTION
NEUTRONS
NUCLEAR FUELS
PERFORMANCE
REACTIVITY COEFFICIENTS
REACTOR CORES
REACTOR DESIGN
REACTOR SAFETY
SODIUM