Thermal-hydraulic analysis of a steam generator tube break transient
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6459785
None
- Research Organization:
- Electric Power Research Institute, 3412 Hillview Avenue, P.O. Box 10412, Palo Alto, CA 94303
- OSTI ID:
- 6459785
- Report Number(s):
- CONF-820609-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 41
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
EPRI
EVALUATION
FLOW MODELS
LOSS OF FLOW
MATHEMATICAL MODELS
REACTOR ACCIDENTS
STEAM GENERATORS
TRANSIENTS
TUBES
VAPOR GENERATORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILERS
COMPUTER CODES
EPRI
EVALUATION
FLOW MODELS
LOSS OF FLOW
MATHEMATICAL MODELS
REACTOR ACCIDENTS
STEAM GENERATORS
TRANSIENTS
TUBES
VAPOR GENERATORS