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

Patent · Fri Dec 31 23:00:00 EST 1982

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
• 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

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