Nuclear power plant volume control box deoxidization testing system and method

Abstract

The invention discloses a nuclear power plant volume control box deoxidization testing system and method. The nuclear power plant volume control box deoxidization testing system comprises a top charging and bottom discharging system, a purging system, an oxygen content adjusting system, a temperature control system and a parameter monitoring system. The nuclear power plant volume control box deoxidization testing system provides functions of upper charging and bottom discharging flow control, temperature adjustment, oxygen content control, nitrogen supply, gas discharging and the like, and based on the functions, achieves a testing mode with intermittent purging and pressured air exhausting. The invention also designs corresponding testing methods for different working conditions and helpsacquire rules of influence of volume control box liquid level, waiting time and purging time on intermittent purging deoxidization effects as well as the rules of influence of standing time on pressurized air exhausting deoxidization effects; by comparing the testing data of two methods, difference of intermittent purging and pressured air exhausting in deoxidization effects can be acquired to provided optimized data support for optimization and adjustment of deoxidization strategies of actual generator units.

Description

technical field [0001] The invention relates to the field of nuclear power, in particular to a test system and method for deoxygenating a capacity control box of a nuclear power plant. Background technique [0002] As one of the nuclear auxiliary systems of PWR nuclear power units, the chemical and volume control system plays an important role in the operation; the volume control function compensates the zero power start-up process of the nuclear power plant from the cold state to the hot state or from the zero power to the hot state. The change in coolant circuit water volume caused by the cold shutdown process. figure 1 It is the control schematic diagram of the primary loop chemical capacity system. In order to maintain a constant water level in the coolant circuit, a chemical capacity system connected to the coolant circuit is provided during normal power generation. The chemical capacity system includes a capacity control box, etc. The pipes and equipment in the coolan...

AI Technical Summary

Problems solved by technology

[0018] At present, there are the following problems in the actual operation of the nuclear power plant using the volume control box to deoxygenate the primary circuit: the current method does not have the relevant method for the deoxygenation performance test of the volume control box, and the deoxygenation operation of the volume control box is carried out according to the empirical parameters. The problem of passing a purge takes up the overhaul time; when the residual air volume in the primary circuit before the purge changes, the deoxygenation strategy cannot be flexibly adjusted according to the actual situation

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