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A Method for Determining Diffusion Coefficient of Tritium Based on Release Rate

A technology of diffusion coefficient and release rate, which is applied in the field of reactor engineering and pebble bed type high temperature gas-cooled reactor, which can solve the problem of less experimental measurement of diffusion coefficient.

Active Publication Date: 2022-02-22
TSINGHUA UNIV
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  • Application Information

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Problems solved by technology

At present, most of the domestic measurements on the diffusion coefficient of tritium are for various stainless steel materials, and there are relatively few experimental measurements and theoretical studies on the diffusion coefficient of tritium in graphite materials.

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  • A Method for Determining Diffusion Coefficient of Tritium Based on Release Rate
  • A Method for Determining Diffusion Coefficient of Tritium Based on Release Rate
  • A Method for Determining Diffusion Coefficient of Tritium Based on Release Rate

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Embodiment Construction

[0036] The present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0037] The present invention is aimed at the existing high temperature gas-cooled reactor source term analysis, the diffusion coefficient is the most important parameter in the study of the transport process of tritium in graphite, but the current theoretical research on the diffusion coefficient of tritium in porous media materials and The experimental results are relatively lacking, and a method and experimental system for determining the tritium diffusion coefficient based on the release rate are proposed. The method and the experimental system obtain the activity of tritium at the detection position in the experimental system at several temperatures within a certain temperature range. The counting rate corresponding to the concentration of 100 degrees Celsius is used to deduce the release rate of tritium from the spherical sample t...

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Abstract

The invention provides a method for determining the tritium diffusion coefficient based on the release rate. The experimental system includes a carrier gas device, a heating furnace and a tritium on-line monitoring device; the method for determining the tritium diffusion coefficient in a spherical porous medium material in this program, which is passed Obtain the counting rate corresponding to the activity concentration of tritium at the detection position in the experimental system at several temperatures within a certain temperature range, deduce the release rate of tritium from the spherical sample to be tested under this temperature condition, and then obtain the tritium at this temperature The specific value of the diffusion coefficient in the spherical sample to be measured under the temperature condition and the general expression of the diffusion coefficient of tritium in the sample of the spherical porous medium material in the corresponding temperature range, that is, to determine the above-mentioned heating temperature range in the sample of the spherical porous medium material Diffusion coefficient of internal tritium.

Description

technical field [0001] The invention relates to the technical field of reactor engineering, in particular to the field of pebble bed high-temperature gas-cooled reactors, in particular to a method for determining tritium diffusion coefficient based on release rate. Background technique [0002] The High Temperature Gas-cooled Reactor (HTGR) and the very high temperature gas-cooled reactor (VHTR) based on it are the closest to commercialization among the six reactor types of the fourth-generation nuclear energy system. reactor. High Temperature Modular Pebble Bed Reactor Project (HTR-PM), designed on the basis of the 10MW high temperature gas-cooled reactor (HTR-10) of Tsinghua University Nuclear Research Institute Built in Rongcheng, Shandong, it is now entering the final stage of commissioning. One of the most important characteristics of a high temperature gas-cooled reactor is the inherent safety characteristic. The so-called inherent safety means that when the reactor...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N15/00G01T1/16G01T1/185
CPCG01N15/00G01T1/16G01T1/185G01N2015/0015
Inventor 王彧谢锋曹建主刘学刚魏利强童节娟董玉杰张作义
Owner TSINGHUA UNIV
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