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

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

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Abstract

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.

Inventors:

Tokarz, Richard D ^[1]

West Richland, WA

Issue Date:: 1983-01-01

Research Org.:: Battelle Memorial Institute, Columbus, OH (United States)

OSTI Identifier:: 864775

Patent Number(s):: 4414177

Assignee:: Tokarz, Richard D. (West Richland, WA)

Patent Classifications (CPCs):: Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS

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Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/30 - Nuclear fission reactors

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C17/02 - Devices or arrangements for monitoring coolant or moderator

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DOE Contract Number:: AC06-76RL01830

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: 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/

Citation Formats


                    Tokarz, Richard D. Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores.  United States: N. p., 1983. 
        Web.

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                    Tokarz, Richard D. Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores.  United States.

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                    Tokarz, Richard D. Sat .  
        "Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores".  United States.  https://www.osti.gov/servlets/purl/864775.

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@article{osti_864775,

  title        = {Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores},

  author       = {Tokarz, Richard D},

  abstractNote = {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.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1983},

  month        = {1}

}

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