Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores
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:
-
- West Richland, WA
- Issue Date:
- 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):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
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
- 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.
Tokarz, Richard D. Liquid level, void fraction, and superheated steam sensor for nuclear reactor cores. United States.
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.
@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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