Unlock instant, AI-driven research and patent intelligence for your innovation.

Nuclear power station high-voltage molten reactor sequence screening method and device, equipment and medium

A screening method, nuclear power plant technology, applied in special data processing applications, instruments, other database retrieval, etc., can solve the difficult test verification of the pressure relief capability of the rapid pressure relief valve, and the pressure relief capability of the rapid pressure relief valve valve cannot be verified one by one And other issues

Active Publication Date: 2021-02-12
NUCLEAR POWER INSTITUTE OF CHINA
View PDF8 Cites 0 Cited by
  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, due to the possibility of countless serious accidents in nuclear power plants, the pressure relief capabilities of the quick relief valves cannot be verified one by one, and due to the particularity of nuclear power plants, it is also difficult to test and verify the pressure relief capabilities of the rapid relief valves

Method used

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
View more

Image

Smart Image Click on the blue labels to locate them in the text.
Viewing Examples
Smart Image
  • Nuclear power station high-voltage molten reactor sequence screening method and device, equipment and medium
  • Nuclear power station high-voltage molten reactor sequence screening method and device, equipment and medium
  • Nuclear power station high-voltage molten reactor sequence screening method and device, equipment and medium

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0049] Such as figure 1 As shown, the present invention provides a nuclear power plant high pressure fusion reactor sequence screening method, which specifically includes the following steps:

[0050] S10: Construct an accident sequence based on the first-level probabilistic safety analysis model, and calculate the occurrence probability of core meltdown caused by each accident in the accident sequence.

[0051] Specifically, a first-level probabilistic safety analysis (PSA) model of internal initiating accidents under power operating conditions is established, and then an accident sequence is constructed according to the first-level probabilistic safety analysis (PSA) model. Since different accidents have different possibilities of core meltdown, after obtaining the accident sequence, the probability of core meltdown caused by each accident in the accident sequence is calculated according to the probability of core meltdown.

[0052] S20: Select a dominant accident sequence ...

Embodiment 2

[0076] Such as image 3 As shown, the difference between this embodiment and Embodiment 1 is that a nuclear power plant high-pressure fusion reactor sequence screening device includes:

[0077] The model analysis module 10 is configured to construct an accident sequence based on a first-level probabilistic safety analysis model, and calculate the occurrence probability of core melting caused by each accident in the accident sequence.

[0078] The dominant accident sequence selection module 20 is configured to select a dominant accident sequence from the accident sequences based on the probability of occurrence.

[0079] The dominant accident sequence screening module 30 is used to compare and screen the dominant accident sequences to obtain effective accident sequences for high-pressure melting reactors.

[0080] The target accident sequence acquisition module 40 is used to obtain the typical sequence of the high-pressure fusion reactor, and add the typical sequence of the hi...

Embodiment 3

[0099] This embodiment provides a computer device, which may be a server, and its internal structure diagram may be as follows Figure 4shown. The computer device includes a processor, memory, network interface and database connected by a system bus. Wherein, the processor of the computer device is used to provide calculation and control capabilities. The memory of the computer device includes a computer-readable storage medium and an internal memory. The computer readable storage medium stores an operating system, computer programs and databases. The internal memory provides an environment for the operation of the operating system and computer programs in the computer-readable storage medium. The database of the computer equipment is used for storing data involved in a method for screening nuclear power plant high-pressure fusion reactor sequences. The network interface of the computer device is used to communicate with an external terminal via a network connection. When...

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

PUM

No PUM Login to View More

Abstract

The invention provides a nuclear power station high-pressure molten reactor sequence screening method and device, equipment and a medium, and the method comprises the steps: building an accident sequence through a first-stage probability safety analysis model, and calculating the probability of occurrence of reactor core melting caused by each accident in the accident sequence; based on the occurrence probability, selecting dominant accident sequences from the accident sequences, and comparing and screening the dominant accident sequences to obtain effective accident sequences of the high-voltage molten reactor; adding the obtained high-voltage melt reactor typical sequence into a high-voltage melt reactor effective accident sequence to form a target accident sequence; and finally, calculating and analyzing the target accident sequence through a nuclear power station integrated analysis program, and selecting a sequence of which the accident process time is less than a preset time threshold and the primary loop pressure is higher than a preset pressure threshold when the pressure vessel fails as a typical serious accident high-pressure molten reactor sequence of the nuclear power station; and obtaining a typical high-pressure melting reactor sequence used for evaluating the capacity of the rapid pressure relief valve. The pressure relief effect of the rapid pressure relief valve in serious accidents of a nuclear power station can be conveniently verified subsequently.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant accident handling, in particular to a screening method, device, equipment and medium for a nuclear power plant high-pressure fusion reactor sequence. Background technique [0002] Nuclear power plant high-pressure fusion reactor refers to the situation in which the pressure vessel is in a high-pressure state when the pressure vessel fails in the severe accident sequence of the nuclear power plant. This situation will cause the core melt to be sprayed into the space inside the containment, which may cause direct heating of the containment (DCH) to damage the safety. Once the containment is incomplete, it will lead to a large amount of leakage of radioactive materials in the containment, and the consequences will be extremely serious. [0003] In order to avoid this situation, the Hualong No. 1 nuclear power plant has set up a quick pressure relief valve specially used for pressure relie...

Claims

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

Application Information

Patent Timeline
no application Login to View More
IPC IPC(8): G06F16/90G06Q10/06
CPCG06F16/90G06Q10/0639Y04S10/50
Inventor 武铃珺王小吉邓纯锐吴清冷贵君青涛邹志强刘丽莉张航张明彭欢欢武小莉
Owner NUCLEAR POWER INSTITUTE OF CHINA