Control method for first criticality of pressurized water reactor of million-kilowatt-class nuclear power station

Abstract

The invention provides a control method for first criticality of a pressurized water reactor of a million-kilowatt-class nuclear power station, which comprises the following steps of: after the refueling treatment of the reactor, carrying out rod lifting treatment to ensure that the final rod position of an R rod is 170 steps and the final rod positions of other rods are 225 steps; after the rod lifting treatment, conducting diluting on a reactor core, and when any one of the conditions that the neutron countdown rate is equal to 0.1 and CB (mes) in a loop is equal to the sum of CB<CRI extrapolation> and 10 ppm is met, stopping the dilution treatment; and adjusting the rod position of the R rod to be greater than or equal to 150 steps until the first criticality is reached. According to the control method for the first criticality of the pressurized water reactor of the million-kilowatt-class nuclear power station, the problem that after refueling, the reactor R rod cannot successfullyreach the criticality at a time from 170 steps to the top (referred to as 'one-time R rod lifting' for short) is effectively and thoroughly solved.

Description

technical field [0001] The invention belongs to the technical field of reactors, in particular to a method for controlling the first criticality of a pressurized water reactor of a million-kilowatt nuclear power plant. Background technique [0002] The pressurized water reactor is a light water nuclear reactor. During the working process of the pressurized water reactor, as the nuclear reaction proceeds, the nuclear raw materials are gradually consumed. Therefore, some raw materials need to be added, that is, refueling. According to the requirements of the Nuclear Safety Regulations "Implementation of the First Criticality Test of a Reactor After Refueling (Dynamic Engraving Rod Technology)" (CTSFUL052), in the procedure of the first critical test after refueling of a pressurized water reactor, the physical test personnel shall start from the standard thermal shutdown after refueling of the reactor. Heap state starts critical operation, first carry out rod lifting operation ...

AI Technical Summary

Problems solved by technology

[0007] The purpose of the present invention is to provide a method for controlling the amount of dilution in the process of pressurized water reactors reaching criticality, aiming to solve the problem in the prior art that the pressurized water reactor fails to lift the R rods once to reach the criticality, and the critical position of the R rods is repeatedly adjusted.

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