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Visual experiment device for melting of nuclear reactor fuel rod and method

A technology for nuclear reactor fuel and experimental equipment, applied in the field of nuclear reactor fuel rod melting visualization experimental equipment, can solve the problems of inability to accurately describe the process and mechanism of serious accidents, difficulties in research and analysis, etc., and achieve simple structure, realizable, and reduced uncertainty Effect

Active Publication Date: 2018-08-24
XI AN JIAOTONG UNIV
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  • Abstract
  • Description
  • Claims
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Problems solved by technology

This makes the research and analysis of the phenomenon very difficult, and the traditional severe accident analysis program simulation faces great challenges in this respect
Because the specific process and phenomenon of fuel rod melting inside the reactor cannot be observed in the existing device, the existing severe accident analysis program can only simulate and analyze the macroscopic lumped parameters, and cannot accurately describe the process and mechanism of the severe accident

Method used

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  • Visual experiment device for melting of nuclear reactor fuel rod and method
  • Visual experiment device for melting of nuclear reactor fuel rod and method
  • Visual experiment device for melting of nuclear reactor fuel rod and method

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Embodiment Construction

[0026] The present invention will be described in detail below by means of the accompanying drawings.

[0027] see figure 1 , figure 2 and image 3 , the visualization experiment method of the present invention is mainly realized through six trapezoidal water-cooling windows and the cooling water circulation system of the high-temperature melting furnace. The experimental method of the invention can visually reveal the melting of the core material and the migration transient behavior characteristics of the molten material, and the obtained visual image data can provide verification for the traditional numerical simulation method. The invention helps to grasp the mechanism of key phenomena and reduces the uncertainty of the core melting process.

[0028] The nuclear reactor fuel rod melting visualization experimental device of the present invention is as figure 1 shown. The nuclear reactor fuel rod melting visualization experimental device includes a high-temperature melt...

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Abstract

The invention provides a visual experiment device for melting of a nuclear reactor fuel rod and a method. The visual experiment device comprises a high-temperature melting furnace provided with a plurality of transparent windows, wherein a test article is vertically arranged in the high-temperature melting furnace; rhenium-molybdenum electrodes are arranged at the upper end and the lower end of the test article respectively and connected with copper electrodes penetrating the side wall of the high-temperature melting furnace; the test article comprises the fuel rod; a tungsten-rhenium heatingrod is arranged in the fuel rod; a cooling water circulation system used for cooling the high-temperature melting furnace is arranged outside the high-temperature melting furnace. By means of the cooling water circulation system for the high-temperature melting furnace, the temperature of the outer side of the furnace body is kept in safe limits, an external high-speed camera can work normally, and a core melting process under a severe accident of a reactor can be simulated realistically. Obtained experiment data can provide verification for the traditional numerical simulation method, and uncertainty of the existing severe accident analyzing procedure is reduced.

Description

technical field [0001] The invention relates to a visualization experiment device and method under severe accident conditions, in particular to a nuclear reactor fuel rod melting visualization experiment device and method, and belongs to the field of experiment measurement visualization methods. Background technique [0002] The material in the reactor will melt into a liquid state when it reaches its own melting point. The eutectic effect of different materials will further reduce this melting temperature. These core material melts will flow downward and enter the lower horizontal position of the reactor core, and there is a certain probability that the area of ​​the reactor coolant flow channel will be reduced. With the further development of severe accidents, core melts continue to accumulate in the coolant flow channels, which will lead to blockages in the flow channels between some fuel assemblies, which will further reduce the cooling capacity of the core and make the...

Claims

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Application Information

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IPC IPC(8): G21C17/08
CPCG21C17/08Y02E30/30
Inventor 田文喜冯唐涛张亚培苏光辉王栋陈荣华王明军王成龙秋穗正罗琦余红星
Owner XI AN JIAOTONG UNIV
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