Analytical model for estimating drag forces on rigid submerged structures caused by LOCA and safety relief valve ramshead air discharges. [BWR]
Technical Report
·
OSTI ID:5175407
Basic information is presented for estimating drag forces on rigid structural members submerged in a pressure suppression pool, caused by either the air discharge from a loss-of-coolant accident (LOCA), or the air bubble oscillation following safey relief valve ramshead discharge. Methods are described for estimating acceleration (unsteady) and standard (velocity-squared) drag force components for a variety of structural geometries.
- Research Organization:
- General Electric Co., San Jose, Calif. (USA). BWR Projects Dept.
- OSTI ID:
- 5175407
- Report Number(s):
- NEDO-21471; TRN: 78-007472
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
LOSS OF COOLANT
CONDENSATION CHAMBERS
STRESSES
PRESSURE SUPPRESSION
CALCULATION METHODS
CONTAINMENT
DEPRESSURIZATION
FLUID FLOW
MATHEMATICAL MODELS
MECHANICAL STRUCTURES
RELIEF VALVES
ACCIDENTS
CONTROL EQUIPMENT
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FLOW REGULATORS
REACTOR ACCIDENTS
REACTORS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
LOSS OF COOLANT
CONDENSATION CHAMBERS
STRESSES
PRESSURE SUPPRESSION
CALCULATION METHODS
CONTAINMENT
DEPRESSURIZATION
FLUID FLOW
MATHEMATICAL MODELS
MECHANICAL STRUCTURES
RELIEF VALVES
ACCIDENTS
CONTROL EQUIPMENT
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FLOW REGULATORS
REACTOR ACCIDENTS
REACTORS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled