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Study of thermal stratification phenomena in an LMFBR hot plenum

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5664027

Compactness is needed for large liquid-metal fast breeder reactor plants to aid in cost reductions. The reactor vessel is particularly large, with a diameter that extends to 20 m, and includes the core, intermediate heat exchangers, pumps, and internal components. The reactor vessel must be made compact. To achieve this, thermal-hydraulic characteristics must be studied in order to provide a safe design. Sodium flow in the hot plenum affects plant dynamics and thermal shock to components. Thermal stratification, especially that occurring after a reactor scram in the hot plenum, and its steep temperature gradient cause thermal fatigue to internal components. Water and sodium negative buoyancy jets have already been studied with simple geometry. The object of this paper is to examine thermal stratification phenomena in a small model with a real hot plenum geometry, experimentally and analytically.

Research Organization:
Hitachi Ltd., Ibaraki, Japan
OSTI ID:
5664027
Report Number(s):
CONF-851115-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 50; ISSN TANSA
Country of Publication:
United States
Language:
English