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Digital control method and system of primary circuit hydrostatic test of pressurized water reactor nuclear power station

A technology for pressurized water reactor nuclear power plant and hydraulic test, which is applied in nuclear power plant control, electrical program control, nuclear power generation, etc., can solve the problems of low control efficiency and poor intuitiveness, and achieve the effect of rapid control

Inactive Publication Date: 2011-08-24
CHINA GENERAL NUCLEAR POWER CORP +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The purpose of the embodiment of the present invention is to provide a digital control method for the hydraulic test of the primary circuit of the PWR nuclear power plant, aiming to solve the existing problems of poor intuition and low control efficiency when controlling the hydraulic test of the primary circuit of the PWR

Method used

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  • Digital control method and system of primary circuit hydrostatic test of pressurized water reactor nuclear power station
  • Digital control method and system of primary circuit hydrostatic test of pressurized water reactor nuclear power station
  • Digital control method and system of primary circuit hydrostatic test of pressurized water reactor nuclear power station

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Embodiment 1

[0027] figure 1 The implementation process of a digital control method for primary circuit hydraulic test of a pressurized water reactor nuclear power plant provided by an embodiment of the present invention is shown, and is described in detail as follows:

[0028] In step S101, the key parameters related to the hydraulic test of the primary circuit of the PWR nuclear power plant, control operation entry and important alarms are all displayed on the hydraulic test control interface.

[0029] see figure 2 , is one example of the hydraulic test control interface provided by the embodiment of the present invention.

[0030] Among them, the key parameters related to the hydraulic test of the primary circuit include but are not limited to:

[0031] The primary circuit pressure normally measures a wide range channel (such as figure 2 RCP037MP and RCP039MP shown in );

[0032] Water pressure test dedicated primary circuit pressure wide, narrow range measurement channel (such as...

Embodiment 2

[0057] image 3 The implementation process of the digital control method for the primary circuit hydraulic test of the pressurized water reactor nuclear power plant provided by the second embodiment of the present invention is shown, and the details are as follows:

[0058] In step S201, the key parameters related to the hydraulic test of the primary circuit of the PWR nuclear power plant, the control operation entry and the layout of important alarms in the hydraulic test control interface are set.

[0059] In the embodiment of the present invention, since the display area of ​​the hydraulic test control interface is limited after all, in order to make the key parameters related to the primary circuit hydraulic test displayed on the hydraulic test control interface, the control operation entry and the important alarm more clearly , Intuitive, convenient for users to quickly control and intervene in the hydraulic test process, it is necessary to pre-set the key parameters rela...

Embodiment 3

[0067] Figure 4 The structure of the digital control system for the primary circuit hydraulic test of the pressurized water reactor nuclear power plant provided by the embodiment of the present invention is shown, and only the parts related to the embodiment of the present invention are shown for convenience of description.

[0068] The system can be used in the DCS control room of a nuclear power plant. It can be a software unit, a hardware unit, or a combination of software and hardware running in these devices. It can also be integrated into these devices as an independent pendant or run on the applications of these devices. system, where:

[0069] The information output unit 1 displays key parameters related to the hydraulic test of the primary circuit, control operation entry and important alarms on the hydraulic test control interface 2 . Among them, the key parameters related to the hydraulic test of the primary circuit, the control operation entry and the specific co...

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Abstract

The invention provides a digital control method and a digital control system of a primary circuit hydrostatic test of a pressurized water reactor nuclear power station, suitable for the nuclear power control field. The method comprises the following steps of: displaying key parameters, a control operation inlet and important alarming related to the primary circuit hydrostatic test on a hydrostatic test control interface; and directly controlling the primary circuit hydrostatic test process through the control operation inlet displayed on the hydrostatic test control interface according to the key parameters displayed by the hydrostatic test control interface. By the method of the invention, the key parameters, the control operation inlet and the important alarming related to the primary circuit hydrostatic test are displayed on the hydrostatic test control interface, and the primary circuit hydrostatic test process is directly controlled through the control operation inlet displayed on the hydrostatic test control interface according to the key parameters displayed by the hydrostatic test control interface, so as to visually and rapidly control the primary circuit hydrostatic test process.

Description

technical field [0001] The invention belongs to the field of nuclear power control, and in particular relates to a digital control method and system for a primary circuit hydraulic test of a pressurized water reactor nuclear power plant. Background technique [0002] The pressurized water reactor nuclear power plant is mainly composed of three parts: the pressurized water reactor, the primary loop system and the secondary loop system. Nuclear fission occurs in a reactor core made of nuclear fuel inside a pressure vessel. Pressurized water reactors use low-enriched uranium as fuel and light water as the coolant and moderator. The heat released by nuclear fission is taken out of the reactor by the high-pressure water flowing through the primary circuit system in the reactor, and the heat is transferred to the water in the secondary circuit in the steamer generator. The steam produced by the heated water drives a steam turbine, which drives a generator to generate electricity...

Claims

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Application Information

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IPC IPC(8): G05B19/418G21D3/00G21C17/00
CPCY02E30/40Y02E30/00Y02E30/30Y02P90/02
Inventor 周创彬黄清武
Owner CHINA GENERAL NUCLEAR POWER CORP
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