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AbstractAbstract
[en] The anticipated behavior of uranium oxide vapor bubbles produced by the capacitor discharge vaporization (CDV) method in the Fuel Aerosol Simulant Test (FAST) Facility is discussed on the basis of relatively simple physical models. Results of calculations for the rate of bubble rise and for heat and mass transfer rates are presented. Parametric studies indicate that future analysis efforts should emphasize the diffusion condensation process and the loss of heat from the bubble by radiation. Transfer of heat in the surrounding sodium is rapid enough that simplified models should be adequate. No important effects were noted in connection with bubble depth, initial quantity of UO2, or initial superheat
Original Title
Fuel Aerosol Simulant Test
Primary Subject
Secondary Subject
Source
1979; 6 p; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, ACTINIDE COMPOUNDS, ALKALI METALS, BREEDER REACTORS, CHALCOGENIDES, COLLOIDS, DISPERSIONS, ELEMENTS, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, METALS, OXIDES, OXYGEN COMPOUNDS, PHASE TRANSFORMATIONS, REACTOR ACCIDENTS, REACTORS, SOLS, URANIUM COMPOUNDS, URANIUM OXIDES
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