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Analysis method of safety injection flow demand in nuclear power plant loss of water accident based on genetic algorithm

A dehydration accident, genetic algorithm technology, applied in the direction of genetic rules, calculation, genetic model, etc., to achieve the effect of large amount of calculation, improve calculation efficiency and reduce calculation time

Active Publication Date: 2022-04-05
XI AN JIAOTONG UNIV
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Problems solved by technology

[0006] In the present invention, relevant research has been carried out to solve the problems existing in the existing safety injection flow demand analysis method

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  • Analysis method of safety injection flow demand in nuclear power plant loss of water accident based on genetic algorithm
  • Analysis method of safety injection flow demand in nuclear power plant loss of water accident based on genetic algorithm
  • Analysis method of safety injection flow demand in nuclear power plant loss of water accident based on genetic algorithm

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Embodiment Construction

[0028] Combine below figure 1 The implementation steps of the genetic algorithm-based analysis method for safety injection flow demand in nuclear power plant loss of water accidents proposed in the present invention are described in detail.

[0029] The first step: select the analysis object and determine the range of the crack spectrum with N groups of crack sizes;

[0030] Step 2: For a loss of water accident of a certain breach size, select the minimum safe water injection volume as the optimization goal; nuclear safety criteria as the limiting condition;

[0031] Step 3: The loss of coolant in the primary circuit of the reactor during the loss of water accident will lead to the deterioration of the core cooling and the increase of the cladding temperature. The magnitude of the flow has a great influence on the cladding temperature, so the magnitude of the safety injection flow depends on the cladding temperature in the core, and the relation table between the cladding tem...

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Abstract

A genetic algorithm-based analysis method for safety injection flow requirements of nuclear power plant loss of water accidents, including: considering the important physical phenomena that affect the evolution of cladding temperature during the transient process of loss of water accidents; searching for the optimal solution based on simulating the natural evolution process Genetic algorithm; based on the loss of water accident analysis program; realizes the process of automatically searching for the optimal safety injection flow requirement under the loss of water accident of the nuclear power plant. Compared with the safety injection flow provided by the safety injection system of the existing nuclear power plant, the method of the present invention considers the relationship between the important parameters in the core and the safety injection flow under the loss of water accident, and realizes the automatic search for the optimal safety injection flow requirement The process can enable the reactor to reduce the water loading of key equipment in the safety injection system under the condition of meeting nuclear safety standards, thereby reducing the construction cost of key equipment in the safety injection system.

Description

technical field [0001] The invention belongs to the technical field of safety analysis of nuclear power plants, and in particular relates to a genetic algorithm-based analysis method for safety injection flow requirements of nuclear power plant loss of water accidents. Background technique [0002] As one of the design basis accidents of PWR nuclear power plants, the loss of coolant accident has always been the focus of nuclear reactor design at home and abroad. When a Loss of Water Accident (LOCA) accident occurs, due to the loss of coolant in the primary circuit of the reactor, if the core is not replenished with water or the amount of water is too small, the heat transfer in the core will deteriorate, threatening the integrity of the core and the safety of the pressure vessel. Safety, so the safety injection flow requirement under the reactor LOCA accident has always been highly valued by the developed countries of nuclear power. [0003] The design of the safety injecti...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06Q10/06G06Q50/06G06N3/12
CPCG06Q10/06315G06Q50/06G06N3/126
Inventor 徐奥迪苟军利党高健鲍辉单建强
Owner XI AN JIAOTONG UNIV
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