A Method for Analyzing Large Breach Accidents in Nuclear Power Plants

Abstract

The invention provides a method for analyzing large break accident of a nuclear power plant. The method comprises the following steps: S1, building a power plant model for catching major physical phenomenon and transient state of real large break loss of coolant accident; S2, analyzing and determining key parameters of the major physical phenomenon and the transient state; S3, classifying the keyparameters, wherein the key parameters are classified into at least conservative assumption parameters, sampling parameters and penalty parameters; S4, setting the most severe condition assumption forthe conservative assumption parameters, and quantitatively analyzing uncertainty of the sampling parameters and the penalty parameters so as to obtain the target parameter value at the set level; S5,selecting a penalty model from the penalty parameters, and performing penalty, so as to realize that the target parameter value obtained through the penalty parameters obtained by penalty treatment includes the target parameter value at the set level. With the adoption of the method in the embodiment, the sampling calculation of a method combining the best estimation and the uncertainty analyzingis reduced, and the conservation margin of deterministic realistic method is decreased.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant accident analysis, in particular to a method for analyzing a large breach accident in a nuclear power plant. Background technique [0002] Reactor coolant loss accident, abbreviated as loss of water accident (LOCA), refers to an accident in which the pressure boundary of the primary circuit is breached or ruptured, or the valve is opened by mistake, resulting in a decrease in the coolant volume of the primary circuit. Among them, the Large Break Loss of Water Accident (LBLOCA), because the accident phenomenon is very complex and the consequences are serious, its margin (the acceptance criterion of the general limit of the accident is the cladding peak temperature, PCT) directly limits the economic efficiency of the nuclear power plant, and is the most One of the important design basis accidents. [0003] In the initial stage of nuclear power development, conservative analysis methods ...

AI Technical Summary

Problems solved by technology

The conservatism of the deterministic realistic method (DRM) is between the conservative analysis method and the best estimate analysis method. However, with the improvement of design requirements, the DRM method is gradually difficult to meet the balance requirements of nuclear power plant design economy and safety. Although this method reduces the overly conservative factors compared with the conservative method, it still has a large unquantified uncertainty, and there is a large margin that can be exploited

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