STUDIES RELATED TO PREDICTING COOLANT BEHAVIOR FOR FAST REACTOR SAFETY
Technical Report
·
OSTI ID:4838436
Various problems related to the prediction of the behavior of liquid sodium coolant in fast reactors during abnormal operating conditions are studied. Included are two-phase flow characteristics, transient forced-convection heat transfer, transient fuel-element heat transfer, and the prediction of coolant behavior in a generalized fast reactor coolant channel. (auth)
- Research Organization:
- United Nuclear Corp., White Plains, N.Y.
- NSA Number:
- NSA-15-030218
- OSTI ID:
- 4838436
- Report Number(s):
- NDA-2147-8
- Country of Publication:
- United States
- Language:
- English
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