Cooling of safety rods in the Savannah River K Reactor during the gamma heating phase of a postulated loss-of-coolant accident
This paper documents the heat-transfer analysis for the safety rod placed in a perforated guide tube during the gamma heating phase of a large-break loss of coolant accident in Savannah River K-reactor. The cooling mechanisms are natural convection to air and radiation to the surrounding structures. The limiting component is the guide tube. The guide tube is shown to remain coolable below its thermal limit for the anticipated reactor powers unless it is contacted by the hotter safety rod. Sample calculations are performed for various contact scenarios, and the results are reported within the paper. The results indicate that the most limiting contact scenario results when the safety rod heats up to its maximum temperature while remaining concentric in the guide tube and then contacts the guide tube. The worse contact location appears to be in line with the slugs-cladding contact and in between the rows of holes in the guide tube.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6669455
- Report Number(s):
- LA-UR-92-3563; CONF-930352-9; N-6-92-R203; ON: DE93003788
- Resource Relation:
- Conference: 2. international conference on nuclear engineering, San Francisco, CA (United States), 21-24 Mar 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
K REACTOR
LOSS OF COOLANT
CONTROL ELEMENTS
COOLING
HEAT TRANSFER
HYDRAULICS
POSITIONING
RADIATION HEATING
REACTOR CHANNELS
REACTOR SAFETY
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEATING
HEAVY WATER MODERATED REACTORS
MECHANICS
PRODUCTION REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SPECIAL PRODUCTION REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220400 - Nuclear Reactor Technology- Control Systems
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors