Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores

Patent · Sat Jan 01 00:00:00 EST 1983

OSTI ID:864775

Tokarz, Richard D ^[1]

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1. West Richland, WA

An apparatus for detecting nominal phase conditions of coolant in a reactor vessel comprising one or more lengths of tubing each leading from a location being monitored to a closed outer end exterior of the vessel. Temperature is sensed at the open end of each length of tubing. Pressure within the tubing is also sensed. Both measurements are directed to an analyzer which compares the measured temperature to the known saturated temperature of the coolant at the measured pressure. In this manner, the nominal phase conditions of the coolant are constantly monitored.

• Research Organization: Battelle Memorial Institute, Columbus, OH (United States)
• DOE Contract Number: AC06-76RL01830
• Assignee: Tokarz, Richard D. (West Richland, WA)
• Patent Number(s): US 4414177
• OSTI ID: 864775
• Country of Publication: United States
• Language: English

Related Subjects

liquid
level
void
fraction
superheated
steam
sensor
nuclear
reactor
cores
apparatus
detecting
nominal
phase
conditions
coolant
vessel
comprising
lengths
tubing
leading
location
monitored
closed
outer
exterior
temperature
sensed
length
pressure
measurements
directed
analyzer
compares
measured
saturated
manner
constantly
void fraction
measured temperature
superheated steam
reactor vessel
nuclear reactor
reactor core
liquid level
measured pressure
phase conditions
reactor cores
heated steam
vessel comprising
/376/976/