Nuclear power station power-losing accident analysis method and system

An analysis method and accident analysis technology, applied in the field of nuclear power, to achieve the effect of good technical effect, less workload, and improved speed of analysis and judgment

Active Publication Date: 2014-02-12
中广核工程有限公司 +1
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Problems solved by technology

[0004] The purpose of the present invention is to: solve the defect of the current artificial fault tree method for power failure analysis method, provide a nuclear power plant power failure accident analysis method and system, which can detect the power supply of each nuclear power plant safety system equipment, each nuclear power plant safety system equipment function Whether it is available, and then judge whether there is a power failure accident in the nuclear power unit, which effectively meets the safety protection requirements of the nuclear power plant

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Embodiment Construction

[0033] In order to make the purpose of the invention, technical solution and beneficial technical effects of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and specific implementation methods. It should be understood that the specific implementations described in this specification are only for explaining the present invention, not for limiting the present invention.

[0034] Please refer to figure 1 , figure 1 A method for analyzing power failure accidents in nuclear power plants is provided, specifically including:

[0035] Step 101, detecting whether the power supply of each nuclear power plant safety system equipment is available.

[0036] Specifically, the structure of the I&C system of a nuclear power plant is divided into the following four types of equipment: field equipment, control processing equipment, operation and information management equipment, and nuclear power plan...

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Abstract

The invention discloses a nuclear power station power-losing accident analysis method and system. The nuclear power station power-losing accident analysis method includes the steps of detecting whether a power source of each nuclear power station safety system device is available or not, analyzing whether each nuclear power station safety system device is available or not if the power source of each nuclear power station safety system device is available, and judging that a nuclear power unit does not have power-losing accidents if each nuclear power station safety system device is available. According to the nuclear power station power-losing accident analysis method, whether the power source and the functions of each nuclear power station safety system device are available or not is detected to further judge whether the nuclear power unit has the power-losing accidents or not, nuclear power station safety protection requirements are effectively met, and the defect that the method that a manual failure tree is used for conducting accident analysis is low in efficiency is solved. In addition, the invention further discloses the nuclear power station power-losing accident analysis system.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and more specifically, the invention relates to a method and system for analyzing power failure accidents of nuclear power plants. Background technique [0002] In the design of nuclear power plants, it is necessary to analyze the design basis accidents, and the power failure accident conditions of nuclear power plants must be considered. The pressurized water reactor nuclear power plant is mainly composed of three parts: the pressurized water reactor, the primary circuit system and the secondary circuit system. The nuclear fission is carried out in the reactor core composed of nuclear fuel in the pressure vessel. Fuel and light water are used as 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 ...

Claims

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Application Information

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IPC IPC(8): G21D3/04
CPCY02E30/40Y02E30/00
Inventor 张颢周创彬曹宁周晓川张立强张建文朱孟子车俊霞
Owner 中广核工程有限公司
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