Assessment of reactor coolant pump instrumentation in support of coolant inventory trend analysis. [PWR]
Technical Report
·
OSTI ID:6289663
Reactor coolant pump motor power and temperature measurements are used by Babcock and Wilcox (B and W) plant owners to calculate void fraction for trending ICC conditions while the pumps are running. In this report, the Nuclear Power Plant Instrument Evaluation (NPPIE) project compares system accuracy, capability, and limitations to measurement requirements using small-break test data and full-scale plant analytical studies. Small-break experimental data show that ICC void fraction calculations are conservative compared to gamma densitometer void fraction measurements in the pipe just upstream of the pumps and liquid level conductivity probes in the reactor vessel. Analytical studies verify that a measure of void fraction at the pumps is conservative relative to the desired coolant inventory trend conditions in the reactor vessel.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6289663
- Report Number(s):
- NUREG/CR-3928; EGG-2333; ON: TI85000797
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLOWMETERS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MEASURING INSTRUMENTS
MECHANICS
METERS
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTORS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLOWMETERS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MEASURING INSTRUMENTS
MECHANICS
METERS
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTORS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS