Patent classifications
G21C17/032
DETECTION APPARATUS, SYSTEM, AND METHOD FOR DETECTION OF COOLANT FLOW RATE AND TEMPERATURE IN A NUCLEAR ENVIRONMENT
A detection apparatus is a flow and temperature measuring device in the form of a tube having a channel positioned parallel to a coolant flow stream and contains a drogue that is firmly attached to a mount within the channel. The mount has a load detection apparatus firmly imbedded near the flow inlet to the tube. The drogue has at least neutral buoyancy in the fluid at the minimum fluid temperature of interest. A change in the buoyancy of the drogue as a function of temperature and a corresponding change in the strain detection apparatus output in the fluid is determined by a combination of simple physics and calibration measurements. The relationship between changes in strain detection apparatus signal output and flow-rate-induced forces applied to the drogue surface are also determined using a combination of simple physics and calibration measurements. A system and method are also described.
DETECTION APPARATUS, SYSTEM, AND METHOD FOR DETECTION OF COOLANT FLOW RATE AND TEMPERATURE IN A NUCLEAR ENVIRONMENT
A detection apparatus is a flow and temperature measuring device in the form of a tube having a channel positioned parallel to a coolant flow stream and contains a drogue that is firmly attached to a mount within the channel. The mount has a load detection apparatus firmly imbedded near the flow inlet to the tube. The drogue has at least neutral buoyancy in the fluid at the minimum fluid temperature of interest. A change in the buoyancy of the drogue as a function of temperature and a corresponding change in the strain detection apparatus output in the fluid is determined by a combination of simple physics and calibration measurements. The relationship between changes in strain detection apparatus signal output and flow-rate-induced forces applied to the drogue surface are also determined using a combination of simple physics and calibration measurements. A system and method are also described.
Heat exchanger and nuclear power plant comprising same
The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.
Heat exchanger and nuclear power plant comprising same
The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.
ACOUSTIC FLOWMETERS AND METHODS OF USING THE SAME
Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Flowmeters include an extension that blocks fluid flow in a path and a detector that detects vibrations caused by vortex shedding in the fluid flow around the extension. The detected frequency of the vibrations determines the flow rate. A Strouhal number may be used to calculate the flow speed using extension surface diameter and detected vortex shedding frequency. Several extensions may cover a range of frequencies and flow speeds. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple, flowmeters of customized physical properties and types are useable together.
ACOUSTIC FLOWMETERS AND METHODS OF USING THE SAME
Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Flowmeters include an extension that blocks fluid flow in a path and a detector that detects vibrations caused by vortex shedding in the fluid flow around the extension. The detected frequency of the vibrations determines the flow rate. A Strouhal number may be used to calculate the flow speed using extension surface diameter and detected vortex shedding frequency. Several extensions may cover a range of frequencies and flow speeds. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple, flowmeters of customized physical properties and types are useable together.
Acoustic flowmeters and methods of using the same
Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Flowmeters include an extension that blocks fluid flow in a path and a detector that detects vibrations caused by vortex shedding in the fluid flow around the extension. The detected frequency of the vibrations determines the flow rate. A Strouhal number may be used to calculate the flow speed using extension surface diameter and detected vortex shedding frequency. Several extensions may cover a range of frequencies and flow speeds. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple, flowmeters of customized physical properties and types are useable together.
Acoustic flowmeters and methods of using the same
Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Flowmeters include an extension that blocks fluid flow in a path and a detector that detects vibrations caused by vortex shedding in the fluid flow around the extension. The detected frequency of the vibrations determines the flow rate. A Strouhal number may be used to calculate the flow speed using extension surface diameter and detected vortex shedding frequency. Several extensions may cover a range of frequencies and flow speeds. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple, flowmeters of customized physical properties and types are useable together.
COOLING WATER STORAGE RESERVOIR AND NUCLEAR REACTOR BUILDING PASSIVE COOLING SYSTEM COMPRISING SAME
The present invention comprises: a storage tank in which cooling water is stored; a partition unit which is disposed inside the storage tank, which partitions the inside of the storage tank into a first storage tank and a second storage tank so that the cooling water can be separated and which has an inlet for causing the cooling water of the second storage tank to naturally introduce into the first storage tank according to the water level difference between the first and second storage tanks; a heat exchanger extending from the first storage tank to the inside of the reactor building to cool the reactor building based on the cooling water of the first storage tank; and a steam discharging unit connected to the heat exchanger and discharging the steam generated in the heat exchanger to the outside of the heat exchanger.
COOLING WATER STORAGE RESERVOIR AND NUCLEAR REACTOR BUILDING PASSIVE COOLING SYSTEM COMPRISING SAME
The present invention comprises: a storage tank in which cooling water is stored; a partition unit which is disposed inside the storage tank, which partitions the inside of the storage tank into a first storage tank and a second storage tank so that the cooling water can be separated and which has an inlet for causing the cooling water of the second storage tank to naturally introduce into the first storage tank according to the water level difference between the first and second storage tanks; a heat exchanger extending from the first storage tank to the inside of the reactor building to cool the reactor building based on the cooling water of the first storage tank; and a steam discharging unit connected to the heat exchanger and discharging the steam generated in the heat exchanger to the outside of the heat exchanger.