A Quantitative Analysis Method and System for Nuclear Power Plant Accident Regulations
An analysis method and technology for nuclear power plants, applied in nuclear power plants, nuclear power plant control, nuclear engineering, etc., can solve problems such as lack of sub-program support evaluation, initial causes of accidents, and limitation of fault types.
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Embodiment 1
[0046] like Figure 1 to Figure 4 As shown, the present invention is a quantitative analysis method for nuclear power plant accident regulations, such as figure 1 As shown, the method includes the following steps:
[0047] S1: Use different levels of working condition selection methods to obtain the working condition spectrum for quantitative evaluation of accident procedures;
[0048] S2: Construct a two-dimensional quantitative evaluation system model according to the obtained working condition spectrum of the quantitative evaluation of accident procedures; the two-dimensional quantitative evaluation system model includes an evaluation system model based on the initial cause event dimension and an evaluation based on the sub-procedure dimension system model;
[0049] S3: Obtain the quantitative analysis requirements of nuclear power plant accident procedures, and automatically select the evaluation system model of the corresponding dimension to perform quantitative analysi...
Embodiment 2
[0091] like Figure 1 to Figure 4 As can be seen, the difference between this embodiment and Embodiment 1 is that this embodiment takes the type of accident "there is a breach of isolation failure on the secondary side of the steam generator" as an example to illustrate the implementation of the quantitative analysis method for the corresponding accident regulations process.
[0092] (1) First, in the process of determining the evaluation work spectrum, through the attached figure 2 The process shown can be obtained:
[0093] (a) A single breach at different positions on the secondary side of the steam generator;
[0094] (b) breaches leading to uncontrolled pressure relief on the secondary side of all steam generators;
[0095] (c) The steam generator breach where the heat transfer tube of the superimposed steam generator is broken;
[0096] Among them, the breach in item (b) is the breach of isolation failure of the secondary side of the steam generator.
[0097] (2) S...
Embodiment 3
[0105] like Figure 1 to Figure 5 As shown, the difference between this embodiment and Embodiment 1 is that this embodiment provides a quantitative analysis system for nuclear power plant accident regulations, such as Figure 5 As shown, the system includes:
[0106] Obtaining the working condition spectrum unit, which is used to adopt different levels of working condition selection methods to obtain the working condition spectrum for quantitative evaluation of accident procedures;
[0107] Constructing an evaluation system unit for constructing a two-dimensional quantitative evaluation system model based on the acquired working condition spectrum for quantitative evaluation of accident procedures; the two-dimensional quantitative evaluation system model includes an evaluation system model based on the initial cause event dimension and a The evaluation system model of the sub-procedure dimension;
[0108] The quantitative analysis unit is used to obtain the quantitative anal...
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