Human factor reliability analysis method for an operator of a digital master control room of a nuclear power station

Abstract

The invention discloses a human factor reliability analysis method for an operator of a digital master control room of a nuclear power station. The invention discloses a human factor reliability analysis method, which relates to the technical field of human factor engineering, and comprises the following steps of: step 1, determining that the dynamic cognitive process of an operator of a digital master control room of a nuclear power station under an accident comprises three cognitive stages of monitoring, decision making and execution, and representing the human factor reliability by the sumof the error rates of the three cognitive stages; step 2, defining an error rate relational expression of each cognitive stage by adopting an exponential structure; step 3, determining influence factors of each cognitive stage in the step 2 and weights of the influence factors at different grades; and step 4, determining a correction coefficient of each cognitive stage in the step 2. According tothe human factor reliability analysis method for the operator of the digital master control room of the nuclear power plant, the digital master control room of the nuclear power plant is taken as thebackground, the human factor reliability analysis method for the operator based on the PSFs weight is provided, the human factor reliability of the accident execution process of the operator can be improved, and errors are reduced.

Description

technical field [0001] The invention relates to the technical field of human factors engineering, in particular to a human factor reliability analysis method for operators in a digital main control room of a nuclear power plant. Background technique [0002] At present, the main control room of nuclear power plants is gradually becoming digital. Compared with the traditional main control room, the digital main control room has obvious advantages. The error mechanism has changed, and some new human factors have emerged, such as: (1) the contradiction between "huge amount of information and limited display"; (2) many information is not fixed on the interface, increasing (3) Since a huge amount of information cannot be displayed on the same interface at the same time, if the operator wants to obtain system-related information, it is inevitable to frequently call the relevant interface and other operations, which greatly increases the The number of operations by the operator in...

AI Technical Summary

Problems solved by technology

[0002] At present, the main control room of nuclear power plants is gradually becoming digital. Compared with the traditional main control room, the digital main control room has obvious advantages. The error mechanism has changed, and some new human factors have emerged, such as: (1) the contradiction between "huge amount of information and limited display"; (2) many information is not fixed on the interface, increasing (3) Since a huge amount of information cannot be displayed on the same interface at the same time, if the operator wants to obtain system-related information, it is inevitable to frequently call the relevant interface and other operations, which greatly increases the The number of operations by the operator increases the possibility of error

(4) Due to the coverage of the interface, the operator cannot observe the changing parameters in time, and the operator is also busy with the completion of various instructions, and cannot detect important alarm information in time, which increases the possibility of accidents

The third-generation HRA method overcomes the defects of the first-generation and second-generation HRA methods, and tries to establish a dynamic HRA method based on simulation, but it also has some imperfections, such as: it cannot handle all behaviors (skilled, rule-based and knowledge-based); the operator lacks the basic theory of power plant status diagnosis; does not fully and properly consider the impact of various behavioral factors on human behavior, and lacks the theoretical basis for how organizational factors affect human reliability

However, these methods are mainly suitable for the traditional main control room, and the traditional operation method is not suitable for the reliability analysis of operators in the digital main control room of nuclear power plants with more complex human factors.

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