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Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station

A technology for protection system and accident analysis, applied in nuclear power plant control, nuclear power plant, nuclear power generation, etc., can solve problems such as failure of the main protection system, failure to mitigate the accident, software common mode failure, etc.

Inactive Publication Date: 2012-07-04
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

However, software common cause failure (SWCCF) may occur in the main protection system of the reactor based on digitalization, which will lead to the complete failure of the main protection system.
If a software common-mode failure occurs and a hypothetical expected transient or design basis accident (hereinafter referred to as: software common-mode superposition accident) occurs superimposed at the same time, the accident cannot be mitigated and will cause serious consequences

Method used

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  • Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station
  • Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station
  • Accident analysis method for digital control diversity protection system of million-kilowatt nuclear power station

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Embodiment Construction

[0041] The present invention will be further described in detail below in conjunction with the drawings and specific embodiments.

[0042] The present invention adds a new simplified reactor diversity protection system (DAS: Diverse Actuation System) to the non-safety level system platform of the Digital Instrument and Control System (DCS) to deal with the common mode failure of the main protection system software of the main protection system platform. Accidents in which the development of the incident is too fast for manual intervention, and the consequences may exceed the acceptance criteria. It also requires a diversity and defense-in-depth analysis of DCS (D3 analysis for short, D3: Diversity and Defense-in-Depth) to ensure that after a software common mode superimposition accident occurs, nuclear power plants can still meet the NRC standard review outline of the US Nuclear Regulatory Commission NUREG-0800, which is the requirement of BTP7-19 "Guidelines for the Evaluation o...

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Abstract

The invention relates to an accident analysis method for a digital control diversity protection system of a million-kilowatt nuclear power station. The method analyzes that a pile main protection system of a 'digital control system (DCS)' in a million-kilowatt nuclear power project is in software common cause failure, and simultaneously, the method superposes the expected operation transient or design basis accident, in the case that an operator has no time to perform manual intervention, the method further researches on adding a diverse actuation system (DAS) in the DCS to ensure the safety of the pile. A DAS scheme is determined after rounded accident analysis of the nuclear power station, and the DAS scheme comprises corresponding automatic protection signals and setting values, so as to guarantee that the accident consequence meets the requirement of a 'diversity and defense in depth (3D)' acceptance criterion.

Description

Technical field [0001] The invention relates to an improved design method for a digital I&C system of a nuclear power plant, in particular to an accident analysis method for a digital I&C system of a million kilowatt nuclear power plant. Background technique [0002] At present, domestic nuclear power plants under construction have adopted the digital instrument control system (DCS) as the control system of the main control room, and its reliability and safety have become the most concerned issues of end users. The digital instrumentation and control system (DCS) of nuclear power plants is generally divided into two platforms, a safety-level main protection system platform and a non-safety-level system platform. The main reactor protection system (RPS: including the emergency shutdown function of the reactor and the function of special safety facilities) adopts digital instrument control. Compared with the traditional analog instrument control system, the value collection is more...

Claims

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Application Information

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IPC IPC(8): G21D3/00G21D3/06
CPCY02E30/40Y02E30/00
Inventor 元一单陈巧艳杨长江詹经祥冯文卿马秀歌汪俊周喆胡伊舟易璇杨海峰姚红霍小东刘新建邱林王世民吕冬宝李文雎陈日罡
Owner CHINA NUCLEAR POWER ENG CO LTD
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