Advanced Two-Phase Flow Instrumentation Program. Quarterly progress report, April-June 1980

Technical Report · Mon Dec 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/6351382· OSTI ID:6351382

Turnage, K. G.; Davis, C. E.; Anderson, R. L.; Miller, G. N.

Work performed to develop and evaluate liquid level sensors for in-vessel use in pressurized water reactors is described. Experiments were performed with three thermal-type level sensors in natural convection to saturated water and steam. Pressures in those tests ranged from 0.1 to 8.6 MPa (15 to 1250 psia). Thermal-type sensors were also tested in steam-water forced convection at low and moderate pressures. Sensor response was found to be insensitive to flow velocity and void fraction but sensitive to the presence or absence of a liquid phase. A series of meetings was held with representatives of three pressurized water reactor vendors regarding research goals and implementation of reactor-vessel monitoring instrumentation.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6351382
• Report Number(s): NUREG/CR-1768; ORNL/NUREG/TM-414; ON: TI86002664
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
LEVEL INDICATORS
TWO-PHASE FLOW
REACTOR COOLING SYSTEMS
RESEARCH PROGRAMS
TEMPERATURE MONITORING
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID FLOW
MEASURING INSTRUMENTS
MONITORING
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled