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Nuclear power station reactor protection system and safety control method therein

A technology for a nuclear power plant reactor and protection system, which is applied in the field of nuclear power plant reactor protection system and safety control, can solve the problems of complex protection system maintenance and regular test plans and high degree of system coincidence

Active Publication Date: 2016-05-11
中广核工程有限公司 +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] In the process of implementing the above-mentioned existing protection system, the inventors found at least the following problems in the prior art: In the existing protection system, the system-level dedicated driver function and the device-level dedicated driver function are mixed in the same subsystem In such a subsystem, the control and processing of protection parameters used by system-level dedicated drive functions, as well as the control and processing of user input instructions used by device-level dedicated drive functions, are mostly implemented by the same device. That is to say, there is a high degree of coincidence between the systems that realize the two functions, which makes the protection system maintenance and periodic testing scheme more complicated

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  • Nuclear power station reactor protection system and safety control method therein
  • Nuclear power station reactor protection system and safety control method therein

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Embodiment 1

[0052] Hereinafter, the nuclear power plant reactor protection system provided by this embodiment will be described with reference to the accompanying drawings. figure 1 It is a schematic structural diagram of a nuclear power plant reactor protection system provided by Embodiment 1 of the present invention.

[0053] Such as figure 1 As shown, the reactor protection system 100 of a nuclear power plant mainly includes an emergency shutdown system (Reactor Trip System, RTS) 10, a dedicated drive system (Engineering Safety Features Actuation System, ESFAS) 20, a safety automation system (Safety Automation System, SAS) 30 and a safety-level ring network SB (Safety System Bus) 40.

[0054] The emergency shutdown system 10 has the following functions: when a design basis accident occurs during the operation of the reactor, it will trigger the shutdown of the reactor to realize the control of the reactivity of the reactor, the discharge of residual heat from the primary circuit, and ...

Embodiment 2

[0067] On the basis of the first embodiment, this embodiment further improves the reactor protection system of the nuclear power plant in the prior art.

[0068] In the prior art, the control sequence for the second-generation pressurized water reactor nuclear power plant is generally only divided into two columns A and B, and the nuclear-level DCS platform is designed with the structure of two columns A and B accordingly. However, with the introduction of the third-generation PWR nuclear power plant, the third-generation PWR nuclear power plant is divided into three control sequences, therefore, the two-column control sequence design of the nuclear power plant reactor protection system in the prior art cannot meet the requirements of the third-generation PWR nuclear power plant. Require.

[0069] For this reason, the dedicated drive system 20 provided in this embodiment is divided into more than three ESFAS sequences, preferably three ESFAS sequences. As described in Embodim...

Embodiment 3

[0076] On the basis of the first or second embodiment above, this embodiment is used to further describe the emergency shutdown system 10 .

[0077] The N protection channels of the emergency shutdown system 10 are connected point-to-point, and each protection channel obtains threshold value comparison results from other N-1 protection channels. Such as figure 1 As shown, RPC-I obtains threshold comparison results from RPC-II to RPC-IV.

[0078] Each protection channel has a hot-standby redundant processor (not shown), and the hot-standby redundant processor obtains a third partial shutdown signal according to the comparison results of N thresholds from the N protection channels. Each protection channel is connected to a shutdown circuit breaker, and the shutdown circuit breaker obtains a third partial shutdown signal from each protection channel, and executes the third partial shutdown signal to control the shutdown of the nuclear power plant.

[0079] More specifically, ea...

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Abstract

The invention provides a nuclear power station reactor protection system and a safety control method therein, and relates to the field of a nuclear power station, for reducing the complexity of a protection system maintenance and regular test scheme. The protection system is provided with an emergency shutdown system dividing into N protection channels, wherein each protection channel obtains protection parameters from a signal preprocessing system and carries out a threshold comparison; a special driving system which is connected with the N protection channels, receives threshold comparison results, performs special driving logic processing according to the threshold comparison results and outputs first special driving instructions for driving an execution mechanism needing to be operated before a reactor reaches a controllable state after a nuclear power plant design reference accident takes place; and a safety automation system which is connected with the special driving system through a safety-grade ring network and generates first equipment-grade control instructions for controlling the execution mechanism needing to be operated when the state of the reactor is converted from the controllable state to a safe shutdown state after the nuclear power plant design reference accident takes place.

Description

technical field [0001] The invention relates to the field of nuclear power plants, in particular to a nuclear power plant reactor protection system and a safety control method therein. Background technique [0002] In order to ensure the safe operation of the nuclear power plant reactor, it is necessary to set up a protection system. The structural design of the protection system is closely related to the overall design of the nuclear power plant, safety classification, and nuclear-level DCS (Digital Control System, digital computer control system) platform design. [0003] In the event of a design basis accident at a nuclear power plant, protection systems are used to bring the reactor to a safe shutdown state. Among them, the design basis accident refers to the accident condition in which targeted measures are taken in the design of the nuclear power plant according to the determined design criteria. The safe shutdown state is the state in which the reactor is stopped in...

Claims

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Application Information

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IPC IPC(8): G21D3/06
CPCG21D3/06Y02E30/00Y02E30/30
Inventor 周叶翔任立永田亚杰史觊汪伟梁玲谭国成王巧燕杨震彭华清陈卫华黄伟军江辉
Owner 中广核工程有限公司
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