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U.S. Department of Energy
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Analytical modeling of core hydraulics and flow management in breeder reactors

Conference ·
OSTI ID:5803769
An analytical model representing the hydraulic behavior of the primary system of fast breeder nuclear reactors is discussed. A computer code capable of detailing the core flow distribution and characterizing the flow and pressure drop in each reactor component is presented. Application of this method to the reactor core thermal-hydraulic design has allowed optimization of the flow management with consequent upgrading in performance, reduction of unnecessary conservatism and very substantial cost savings. Typical quantitative examples are presented.
Research Organization:
Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.
DOE Contract Number:
EY-76-C-15-2395
OSTI ID:
5803769
Report Number(s):
CONF-790934-1
Country of Publication:
United States
Language:
English