Universal treatment of plumes and stresses for pressurized thermal shock evaluations
Technical Report
·
OSTI ID:5035521
- California Univ., Santa Barbara, CA (United States). Dept. of Chemical and Nuclear Engineering
The thermal field in a reactor vessel downcomer and resulting thermal/stress response in the adjacent reactor vessel wall during high-pressure safety injection are examined, especially with regard to departures from one-dimensional behavior. Similarity solutions for the stratification (in the cold leg) that creates the downcomer plumes, and scaling considerations for the thermal conduction and stress fields in the vessel wall are developed to provide generalized criteria for the adequacy of the one-dimensional treatment.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; California Univ., Santa Barbara, CA (United States). Dept. of Chemical and Nuclear Engineering
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5035521
- Report Number(s):
- NUREG/CR-5854; ON: TI92017874
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
PLUMES
STRESSES
REACTOR VESSELS
THERMAL SHOCK
FLOW MODELS
FLUID FLOW
H CODES
HEAT TRANSFER
HYDRAULICS
R CODES
REACTOR SAFETY
STRATIFICATION
STRESS ANALYSIS
THERMAL ANALYSIS
TRANSIENTS
VOIDS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
FLUID MECHANICS
MATHEMATICAL MODELS
MECHANICS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
PLUMES
STRESSES
REACTOR VESSELS
THERMAL SHOCK
FLOW MODELS
FLUID FLOW
H CODES
HEAT TRANSFER
HYDRAULICS
R CODES
REACTOR SAFETY
STRATIFICATION
STRESS ANALYSIS
THERMAL ANALYSIS
TRANSIENTS
VOIDS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
FLUID MECHANICS
MATHEMATICAL MODELS
MECHANICS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers