4 results about "Nuclear reactor coolant" patented technology

The present application belongs to the field of nuclear power plant reactor coolant pump motor unit installation and test, and particularly relates to a nuclear reactor coolant pump motor rotor reset measuring device and method, which comprises: a detection assembly and a data processing assembly; the detection assembly is multiple sets, and is arranged on the upper slip rotor and the lower flywheel of the motor, respectively; the data processing assembly comprises a control box and a remote control PC end; the detection assembly, the control box and the remote control PC end are connected in sequence, the detection assembly measures and collects the rotor position, generates measurement and collection data, and transmits the data to the control box; the control box receives the measurement and collection data transmitted by the detection assembly, processes the data, generates measurement result data, and transmits the data to the remote control PC end; and the remote control PC end receives the measurement result data transmitted by the control box, and displays the data. The device has simple structure and convenient operation, and can realize the rotor reset after the no-load test of the reactor coolant pump motor.

The present application belongs to the technical field of nuclear reactor fuel element thermal hydraulic, and particularly relates to a method for realizing non-uniform temperature distribution of a fuel element base body. The method comprises: arranging thermocouples for temperature measurement at different positions on the side surface of the base body and the surfaces of the electric heating element and the metal gas cooling pipe, and monitoring the temperature distribution of the fuel element base body structure in real time. The method provided by the present application considers the influence of the coolant flow in the real nuclear reactor fuel element on the temperature distribution of the base body, divides the different channels in the fuel element base body into heating channels and cooling channels by function division, integrates the electric heating element in the heating channels to simulate the heat release of the nuclear reactor fuel element, integrates the metal gas cooling pipe in the cooling channels to simulate the cooling effect of the nuclear reactor coolant, and thus realizes more realistic simulation of the temperature field distribution of the nuclear reactor.

This invention discloses a quantitative prediction method for scouring corrosion of flow components in lead-bismuth main pumps, belonging to the field of corrosion calculation technology for nuclear reactor coolant circulation equipment. The invention employs a Kays94 Prandtl number model for turbulent flow, modified for computational fluid dynamics simulation, to obtain the surface temperature, oxygen concentration, flow velocity, and wall shear stress of the flow components. Then, a coupled scouring corrosion model is constructed, incorporating oxide layer growth, reduction removal, and flow erosion removal. Finally, the flow field parameters are input into the coupled model and solved using the oxygen transport equation to quantitatively calculate the magnetite layer thickness, spinel layer thickness, and steel matrix loss. This invention achieves a leap from qualitative judgment to quantitative prediction, directly outputting parameters such as corrosion rate and thickness distribution, providing a quantitative basis for lead-bismuth pump structure optimization, life assessment, and corrosion control.

The embodiment of the application discloses a kind of performance test method and system of nuclear reactor coolant pump, it is related to nuclear reactor technical field, method includes: obtaining the first measurement sequence of main pump in nuclear reactor under the condition of power failure, and the second measurement value of main pump under the condition of power failure moment, first measurement sequence includes multiple first measurement values;According to first measurement sequence and second measurement value, determine the initial drop curve of coolant flow in primary loop;According to initial drop curve, and the coolant steady flow of each coolant loop in primary loop under different power of nuclear reactor, determine target drop curve;According to target drop curve, first preset coasting flow curve and second preset coasting flow curve, determine whether the performance test result of main pump meets the safety analysis requirement, can improve the accuracy of main pump coasting performance test.