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Method for simulating characteristics of nuclear reactor gravity type passive safety injection equipment

A technology of nuclear reactor and equipment characteristics, applied in the field of nuclear reactors, can solve problems such as leakage of radioactive substances, burning of fuel element cladding, etc., and achieve the effect of accurate cooling capacity

Active Publication Date: 2020-02-21
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

As the primary circuit coolant continues to be sprayed from the breach, the liquid level in the reactor core continues to drop. After the core is exposed, the decay heat power of the fuel element may burn the fuel element cladding, resulting in the leakage of radioactive substances.

Method used

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  • Method for simulating characteristics of nuclear reactor gravity type passive safety injection equipment
  • Method for simulating characteristics of nuclear reactor gravity type passive safety injection equipment
  • Method for simulating characteristics of nuclear reactor gravity type passive safety injection equipment

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Experimental program
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Embodiment 1

[0041] Such as figure 1 As shown, the test device of the present invention mainly includes a reactor pressure vessel simulation body, a passive safety injection equipment simulation body, a valve, a flow meter and a loop pipeline, and the test device is proportionally reduced according to the prototype. Determine the area reduction factor of all equipment and pipelines in the test device as λ, and then the flow channel area of ​​all equipment and pipelines in the test device can be obtained.

[0042] A method for simulating the characteristics of nuclear reactor gravity-type passive safety injection equipment, comprising the following steps:

[0043] 1) Obtain the number of simulation criteria:

[0044] a1), according to the mass conservation equation and energy conservation equation to obtain the formula describing the safety injection process:

[0045]

[0046] In the formula, A E is the flow cross-sectional area of ​​the safety injection pipeline outlet, A T is the f...

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PUM

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Abstract

The invention discloses a method for simulating the characteristics of nuclear reactor gravity type passive safety injection equipment. The method comprises the following steps: 1) obtaining a simulation criterion number: establishing a mass and momentum conservation equation for gravity driven safety injection, and reasonably simplifying and nondimensionalizing an equation to obtain the simulation criterion number for simulating the characteristics of prototype passive safety injection equipment; 2) ensuring that simulation criterion numbers of the test device and prototype equipment are thesame, and obtaining a simulation proportion of main parameters of the test device; and 3) on the premise that the pressure vessel, reducing the passive safety injection equipment and the safety injection pipeline are reduced in equal proportion, setting a test device and controlling parameters according to the requirements of simulation proportion and equal-height simulation. According to the invention, the safety injection characteristics of the gravity type passive safety injection equipment and the cooling capacity of the reactor core after the water loss accident of the nuclear reactor canbe accurately simulated in real time according to a small-scale experiment scale proportion.

Description

technical field [0001] The invention relates to the field of nuclear reactors, in particular to a method for simulating the characteristics of nuclear reactor gravity-type passive safety injection equipment. Background technique [0002] When a loss of water accident occurs in a nuclear reactor, the pressure in the primary circuit drops sharply, and then the control rod falls to implement an emergency core, and the main pump stops running after a short idle. As the coolant in the primary circuit continues to be sprayed from the breach, the liquid level in the reactor core continues to drop. After the core is exposed, the decay heat power of the fuel elements may burn the fuel element cladding, resulting in the leakage of radioactive substances. Therefore, when the reactor loses water accident, injecting coolant into the reactor pressure vessel to effectively cool the core is an important measure to prevent the leakage of radioactive materials in the nuclear reactor. [0003...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F17/11
CPCG06F17/11
Inventor 彭传新昝元锋白雪松张妍卓文彬闫晓
Owner NUCLEAR POWER INSTITUTE OF CHINA