Published 1979 | Version v1
Report Open

Analysis of the heat and mass transfer processes of UO2 bubble in sodium

Description

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Additional titles

Augmented title (English)
Fuel Aerosol Simulant Test

Publishing Information

Imprint Pagination
6 p.
Report number
CONF-790816--30

Conference

Title
International meeting on fast reactor safety technology.
Dates
19 - 23 Aug 1979.
Place
Seattle, WA, USA.