Coincident steam generator tube rupture and stuck-open safety relief valve carryover tests: MB-2 steam generator transient response test program
In PWR steam generator tube rupture (SGTR) faults, a direct pathway for the release of radioactive fission products can exist if there is a coincident stuck-open safety relief valve (SORV) or if the safety relief valve is cycled. In addition to the release of fission products from the bulk steam generator water by moisture carryover, there exists the possibility that some primary coolant may be released without having first mixed with the bulk water - a process called primary coolant bypassing. The MB-2 Phase II test program was designed specifically to identify the processes for droplet carryover during SGTR faults and to provide data of sufficient accuracy for use in developing physical models and computer codes to describe activity release. The test program consisted of sixteen separate tests designed to cover a range of steady-state and transient fault conditions. These included a full SGTR/SORV transient simulation, two SGTR overfill tests, ten steady-state SGTR tests at water levels ranging from very low levels in the bundle up to those when the dryer was flooded, and three moisture carryover tests without SGTR. In these tests the influence of break location and the effect of bypassing the dryer were also studied. In a final test the behavior with respect to aerosol particles in a dry steam generator, appropriate to a severe accident fault, was investigated.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Technology Systems Div.; Central Electricity Generating Board, Leatherhead (UK). Technology Planning and Research Div.; Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Systems Safety; Electric Power Research Inst. (EPRI), Palo Alto, CA (United States)
- OSTI ID:
- 6658777
- Report Number(s):
- NUREG/CR-4752; EPRI-NP-4787; TPRD/L-3009-R86; WCAP-11226; ON: TI87900562
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR SAFETY
STEAM GENERATORS
TUBES
FAILURES
RUPTURES
BLOWDOWN
DATA ACQUISITION SYSTEMS
ENGINEERING DRAWINGS
EVALUATION
EXPERIMENTAL DATA
FAULT TREE ANALYSIS
FISSION PRODUCTS
FLOW RATE
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MEASURING INSTRUMENTS
MONITORING
PERFORMANCE TESTING
RADIOACTIVE EFFLUENTS
REACTOR COOLING SYSTEMS
RELIEF VALVES
RISK ASSESSMENT
SAMPLERS
SYSTEM FAILURE ANALYSIS
TEST FACILITIES
ACCIDENTS
BOILERS
CONTROL EQUIPMENT
COOLING SYSTEMS
DATA
DIAGRAMS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
INFORMATION
ISOTOPES
MATERIALS
MECHANICS
NUMERICAL DATA
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SYSTEMS ANALYSIS
TESTING
VALVES
VAPOR GENERATORS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled