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Transient accident analysis of a supercritical carbon dioxide Brayton cycle energy converter coupled to an autonomous lead-cooled fast reactor.

Journal Article · · Nucl. Eng. Des.

The supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle is a promising advanced alternative to the Rankine 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.

Research Organization:
Argonne National Laboratory (ANL)
Sponsoring Organization:
SC; NERI
DOE Contract Number:
AC02-06CH11357
OSTI ID:
939561
Report Number(s):
ANL/NE/JA-60328
Journal Information:
Nucl. Eng. Des., Journal Name: Nucl. Eng. Des. Journal Issue: 8 ; Aug. 2008 Vol. 238; ISSN NEDEAU; ISSN 0029-5493
Country of Publication:
United States
Language:
ENGLISH