Method for calculating heat power of pressurized water reactor in nuclear power station

Abstract

The invention discloses a method for calculating the heat power of a pressurized water reactor in a nuclear power station. The pressurized water reactor comprises a four-loop EPR (European pressurized reactor) core, wherein the heat power value of each loop is calculated at first, and then the heat power values of the four loops are added to obtain the heat power value of the EPR core. The method for calculating the heat power of the loops comprises the following steps: comparing actual rotary speed of a pump with theoretical rotary speed of the pump to obtain the pump efficiency; subtracting cold-section liquid-phase enthalpy from hot-section liquid-phase enthalpy to obtain enthalpy rise value of each loop; multiplying the enthalpy rising value by the rated flow of the pump within unit time to obtain an actual volume flow value in each loop; multiplying each actual volume flow value by cold-section liquid-phase water density value to an obtain actual mass flow value in each loop; multiplying the pump efficiency by each actual mass flow value so as to obtain a result and dividing the result by 1000 to obtain a heat power value of each loop. According to the method, the heat power calculation of three loops is expanded to the heat power calculation of the four loops on the basis of a heat power calculation principle, and an existing heat power calculation method can be completely substituted. Therefore, the method can be well suitable for being used for calculating the EPR heat power.

Description

technical field [0001] The invention relates to the field of nuclear power, in particular to a calculation method capable of calculating the thermal power of a multi-loop pressurized water reactor. Background technique [0002] When calculating the power of the reactor, since the detector can only be installed in the biological shielding layer outside the core and cannot be directly measured, it can only be calculated by the thermal power between the loops of the PWR. In each loop of the reactor, the pipeline between the outlet of the reactor pressure vessel and the inlet of the steam generator is called the hot section, and the pipeline between the main pump and the inlet of the pressure vessel is called the cold section. The principle of thermal power calculation is: Under the working absolute pressure of the normal operation of the reactor coolant system, the liquid-phase water in the cold section flows through the heat exchanger for heat exchange. The heat transfer can b...

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Problems solved by technology

[0004] In order to solve the problem in the prior art that the calculation of the thermal power of the pressurized water reactor of the nuclear power plant cannot realize the calculation of the thermal power of the four-loop circuit, the present invention provides a method that can realize the calculation of the thermal power of the four-loop circuit of the pressurized water reactor of the nuclear power plant

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