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Non-destructive characterization method, especially for characterizing particles of nuclear fuel for a high-temperature reactor

A characterization and particle technology, applied in reactors, nuclear reactor monitoring, instruments for radiological diagnosis, etc., can solve the problems of destroying fuel particles and realizing complex problems

Inactive Publication Date: 2009-08-26
FRAMATOME ANP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] The disadvantage of this method is the use of toxic liquids
Also, this characterization method is slow and destroys the fuel particles being characterized
Finally, the implementation of this method was found to be extremely complex, since the fragments of each layer had to be separated and identified one by one

Method used

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  • Non-destructive characterization method, especially for characterizing particles of nuclear fuel for a high-temperature reactor
  • Non-destructive characterization method, especially for characterizing particles of nuclear fuel for a high-temperature reactor
  • Non-destructive characterization method, especially for characterizing particles of nuclear fuel for a high-temperature reactor

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Experimental program
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Embodiment Construction

[0031] figure 1 The principle shows particles 1 of nuclear fuel used in high temperature or ultra-high temperature reactors (HTR / VHTR).

[0032] According to the traditional way, the particles 1 are usually spherical, and from the inner layer to the outer layer include:

[0033] -A core of fissile material 3, which is for example based on UO 2 (It can be other types of fissile material, such as UCO, or UO 2 And UC 2 mixture),

[0034] -Porous pyrolytic carbon layer 5,

[0035] -The first dense pyrolytic carbon layer 7,

[0036] -Silicon carbide layer 9 (or another ceramic such as zirconium carbide), and

[0037] -The second dense pyrolytic carbon layer 11.

[0038] When such particles are used, porous pyrolytic carbon acts as a reservoir for fission gas, silicon carbide acts as a barrier to prevent the diffusion of solid fission products, and dense pyrolytic carbon provides mechanical strength of fission gas under pressure.

[0039] The diameter of the core 3 is, for example, ab...

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Abstract

The aim of the method is to characterize an element (21) comprising a plurality of superposed layers separated from one another by interfaces. It comprises at least the following steps: The element (21) is illuminated with radiation (15) emitted by a source (13); radiation (23) transmitted through the element (21) is collected on a detector (17), this transmitted radiation forming an experimental image of the element (21) on the detector (17), the detector (17) being placed at such a distance from the element (21) that interference fringes appear on the experimental image at the interfaces between the layers; and an approximate value of at least one physical characteristic of at least one given layer is determined by calculation from the experimental image, the determination step being implemented by minimizing the difference between the experimental image and a simulated image of at least part of the experimental image of the element (21).

Description

Technical field [0001] The present invention generally relates to a non-destructive characterization method, and particularly relates to a non-destructive characterization method for nuclear fuel particles used in high-temperature reactors. [0002] More specifically, according to the first aspect, the invention relates to a method for characterizing an element comprising a plurality of superimposed layers separated from each other by an interface. Background technique [0003] The nuclear fuel particles used in high-temperature nuclear reactors are substantially spherical and include a fission core (core) that is coated with a dense and porous layer of pyrocarbon and a ceramic material, such as Silicon carbide or zirconium carbide. The determination of the density of each layer that composes fuel particles is a parameter necessary for qualification of the fuel. [0004] The most common method used for this purpose is the flotation method. Sample multiple reference particles from...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01N23/02G01N23/20G21C17/06G01B11/06G01B15/02
CPCG21K2207/005G21C17/06G21Y2002/304G21Y2004/40G21Y2002/202G01N2223/615G01B15/025A61B6/484Y02E30/30
Inventor J·班彻特D·蒂西耶
Owner FRAMATOME ANP