Transient Accident Analysis of a Supercritical Carbon Dioxide Brayton Cycle Energy Converter Coupled to an Autonomous Lead-Cooled Fast Reactor

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:20995586

Moisseytsev, Anton; Sienicki, James J ^[1]

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

The Supercritical Carbon Dioxide (S-CO{sub 2}) Brayton Cycle is a promising advanced alternative to the Rankine saturated steam cycle and recuperated gas Brayton cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO{sub 2} Brayton cycle coupled to an autonomous, natural circulation Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios. (authors)

• Research Organization: The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
• OSTI ID: 20995586
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ACCIDENTS
BRAYTON CYCLE
CARBON DIOXIDE
COMPUTER CODES
DESIGN
FAST REACTORS
HEAT SINKS
LEAD
NATURAL CONVECTION
NUCLEAR ENERGY
PERFORMANCE
SAFETY
SIMULATION
STEAM
TRANSIENTS