Consequences of non-wetting behavior of Mark 16B and Mark 22 assemblies: (Deleted Version)
In the NED Weekly Highlights date December 19, 1985, I stated that the non-wetting behavior of Mark 16B and Mark 22 assemblies might have negative consequences on ECS power limits and discharge cooling of reactor assemblies. My statement was based on heat transfer experiments with a stainless steel heater. Recent calculations for discharge cooling show that the higher thermal conductivity of the aluminum-uranium alloy used in fuel tubes would compensate for the non-uniform distribution of coolant found in non-wetting tubes. I conclude that wettability is not a factor in discharge cooling. Assembly powers after a LOCA would be higher than discharge powers. An approximate calculation of ECS power limits concluded that non-wetting Mark 16B and Mark 22 assemblies would limit assembly power in the winter. The powers of the hottest Mark 16B and Mark 22 assemblies would have to be limited to 83% and 85%, respectively, of the highest powers run in recent years. I do not recommend that any action be taken until the research is completed and reviewed by peers. Work on a new melting model for LOCA conditions and both wetting and non-wetting surfaces is my highest priority work.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 6701551
- Report Number(s):
- CORR-880273; ON: DE89002442
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FUEL ELEMENTS
WETTABILITY
ECCS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
REACTOR SAFETY
SAVANNAH RIVER PLANT
ACCIDENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220300* - Nuclear Reactor Technology- Fuel Elements
220900 - Nuclear Reactor Technology- Reactor Safety