A system for determining a power generated by an assembly for a nuclear reactor includes a subsystem for measuring a flow rate of a heat-transfer fluid including a body wherein the fluid flows, at least one rotor configured to be rotated by the fluid, and a device for measuring a rotation speed of the rotor. The device for measuring includes an optical module configured to transmit an incident light radiation on blades of the rotor, in a direction substantially perpendicular to an axis of rotation of the rotor, and to receive a reflected light radiation coming from the blades. The system further includes a subsystem for measuring a temperature of the fluid at an inlet and at an outlet of the assembly. The system is configured to determine the flow rate of the fluid, and to determine a power generated by the assembly.

The invention relates to rod thermometer device for detecting a temperature, including a plurality of temperature-sensitive elements and a protective sheath having an axis X in which the sensitive elements are partially inserted. The sheath is made of a metal constituting one of the two metals of a thermocouple, and the sensitive elements of a plurality of wires made of a metal other than that of the sheath and constituting the other one of the two metals of a thermocouple, one of the ends of each one of the wires being welded inside the sheath forming a junction for measuring a given thermocouple, the welded ends of the wires being distributed along a plurality of axial and azimuth positions relative to the axis X inside the sheath, each one of the wires extending out of the sheath by at least one of the ends thereof.

The invention relates to rod thermometer device for detecting a temperature, including a plurality of temperature-sensitive elements and a protective sheath having an axis X in which the sensitive elements are partially inserted. The sheath is made of a metal constituting one of the two metals of a thermocouple, and the sensitive elements of a plurality of wires made of a metal other than that of the sheath and constituting the other one of the two metals of a thermocouple, one of the ends of each one of the wires being welded inside the sheath forming a junction for measuring a given thermocouple, the welded ends of the wires being distributed along a plurality of axial and azimuth positions relative to the axis X inside the sheath, each one of the wires extending out of the sheath by at least one of the ends thereof.

A method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30). The lubrication fluid is injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).

A method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30). The lubrication fluid is injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).

A device for centering a temperature measurement device inside a tube reactor that will be filled with catalyst, including a single inflatable bladder mechanically and fluidically attached to a centering ring.

A device for centering a temperature measurement device inside a tube reactor that will be filled with catalyst, including a single inflatable bladder mechanically and fluidically attached to a centering ring.

A method for in-situ measuring of a liquidus temperature of a supply of the molten salt, includes withdrawing a sample of the molten salt from the supply, placing it into a sample container, and cooling the sample of the molten salt from a first temperature above the liquidus temperature of the molten salt to a second temperature at which at least a portion of the sample of the molten salt solidifies. The method includes taking a plurality of temperature measurements of the sample of the molten salt during cooling of the sample and determining the liquidus temperature of the molten salt from the measurements. The sample of the molten salt is heated from the second temperature to the first temperature and returned to the supply of the molten salt.

A method for in-situ measuring of a liquidus temperature of a supply of the molten salt, includes withdrawing a sample of the molten salt from the supply, placing it into a sample container, and cooling the sample of the molten salt from a first temperature above the liquidus temperature of the molten salt to a second temperature at which at least a portion of the sample of the molten salt solidifies. The method includes taking a plurality of temperature measurements of the sample of the molten salt during cooling of the sample and determining the liquidus temperature of the molten salt from the measurements. The sample of the molten salt is heated from the second temperature to the first temperature and returned to the supply of the molten salt.

A method and a system for performing real-time, continuous, measurements of the boron concentration in the water entering a nuclear reactor coolant system. The invention utilizes knowledge of the impact that boron contained in liquid water has on the attenuation of acoustic or ultrasonic waves. This information, coupled with radiation damage resistant and high temperature operability capable transmitter and receiver equipment, provides the means to place the measurement system sensors and signal processing electronics on the reactor coolant system charging flow piping or the hot leg or cold leg of the reactor coolant loop. This will allow the reactor operator to directly monitor both the reactor coolant system boron concentration value and detect changes in the reactor coolant system boron concentration relative to a reference value as they occur.