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Preparation method of post-irradiation reactor structure material thermal conductivity test sample and sample box

A structural material and a technology for a reactor, which are applied in the field of a preparation method and a sample box for a thermal conductivity test sample of a reactor structural material after irradiation, can solve the problem that the thermal conductivity sample is difficult to prepare, the thermal conductivity sample is not easy to fix, and Uneven heat conduction and other problems, to achieve batch irradiation and preparation, avoid uneven clamping force, and secure the effect

Active Publication Date: 2021-03-02
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The technical problem to be solved by the present invention is: using the traditional method to prepare the thermal conductivity sample of the reactor structural material after irradiation, there are problems such as relatively difficult preparation and low yield. The present invention provides a post-irradiation reactor that solves the above problems The preparation method and sample box of the thermal conductivity test sample of the structural material effectively solve the problems of difficulty in preparing the thermal conductivity sample of the reactor structural material after irradiation, poor dimensional accuracy, low yield and difficulty in mass production; and Avoid problems such as the thermal conductivity sample is not easy to fix in the irradiation device and the heat conduction is uneven, especially suitable for the preparation of small-sized thermal conductivity samples after irradiation

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  • Preparation method of post-irradiation reactor structure material thermal conductivity test sample and sample box

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Embodiment 1

[0043] This embodiment provides a method for preparing a test sample for thermal conductivity of reactor structural materials after irradiation, and the preparation steps are as follows:

[0044] Step 1: Take unirradiated reactor structural materials and process them to obtain prefabricated samples. The processing is to directly use a lathe or wire electric discharge to process a prefabricated sample with a diameter of Ф6mm×2mm. The size of the prefabricated sample meets the requirements of the thermal conductivity test. Such requirements.

[0045] Step 2, put the sample obtained in step 1 into a closed container for packaging, clamp the closed container with a clamp, load it into the irradiation device and put it into the pile for irradiation test; during this step, one or Multiple prefabricated samples are placed in a closed container at the same time, and they are irradiated together to achieve batch irradiation and preparation.

[0046] Step 3, after the irradiation is ov...

Embodiment 2

[0048] This embodiment provides an irradiated sample box, which is used as a closed container in the preparation method of a test sample for thermal conductivity of reactor structural materials after irradiation provided in Example 1, and the prefabricated sample is placed in the sample inside the box. The irradiation sample box includes a lower base 2 and an upper cover plate 1. At least one groove 4 is provided on the upper surface of the lower base 2. The groove 4 is used to accommodate prefabricated samples. Setting multiple grooves 4 can realize batch preparation; The lower surface of the upper cover plate 1 is attached and fixed to the upper surface of the lower base 2 .

Embodiment 3

[0050] Further improvement on the basis of Example 2, the inner diameter of the groove 4 satisfies: the inner wall of the groove 4 is in interference fit contact with the outer wall of the prefabricated sample, and the upper surface of the lower base 2 and the port of the groove 4 are also An additional groove 5 is provided, and the additional groove 5 communicates with the groove 4, and the additional groove 5 is used to fill with heat-conducting material, such as aluminum material, before irradiation. The upper surface of the lower base 2 is provided with a protrusion I / or groove I, and the lower surface of the upper cover plate 1 is provided with a corresponding groove II / or protrusion II; the upper protrusion I of the lower base 2 and the upper cover plate 1 The groove II of the upper cover 1 fits and splices, or the protrusion II of the upper cover 1 fits and splices with the groove I of the lower base 2 .

[0051] The upper cover 1 and the lower base 2 are fastened and c...

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Abstract

The invention discloses a preparation method of a post-irradiation reactor structure material thermal conductivity test sample. The method sequentially comprises the following steps: step 1, processing a non-irradiated reactor structure material to obtain a prefabricated sample, the size, surface smoothness and the like of the prefabricated sample needing to satisfy the requirements of the thermalconductivity test sample; step 2, placing the sample obtained in the step 1 in a closed container, clamping the closed container through a clamping block, loading the closed container into an irradiation device, and putting the irradiation device into a reactor for irradiation test; and step 3, after irradiation is finished, taking out the irradiated sample in the closed container, and directly applying the irradiated sample to thermal analysis and detection. According to the invention, the problems of high preparation difficulty, poor dimensional precision, low yield, difficulty in batch production and the like of the existing irradiated reactor structure material heat conductivity sample are effectively solved; the problems that the heat conductivity sample is not easy to fix in the irradiation device and heat conduction is uneven are solved, and the method is particularly suitable for preparing the small-size irradiated heat conductivity sample.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel cycle, in particular to a method for preparing a test sample of thermal conductivity of reactor structural materials after irradiation and a sample box. Background technique [0002] Reactor structural materials are an important part of reactor safety and play a vital role in the safe operation of reactors. With the advancement of nuclear power technology, reactor life extension and fuel burnup have gradually become a new trend in the development of nuclear power, and higher requirements have been placed on the reliability of reactor structural materials under severe working conditions. , especially the thermal conductivity of reactor structural materials after irradiation, is one of the important performance indicators to measure the reliability of reactor structural materials. For example, under normal service conditions, the fuel pellets are affected by the chain nuclear fission reaction,...

Claims

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Application Information

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IPC IPC(8): G01N25/20G01N25/18G01N1/44G01N1/28
CPCG01N25/18G01N25/20G01N1/28G01N1/286G01N1/44G01N2001/2873G01N2001/2866Y02E30/30
Inventor 张伟吴璐伍晓勇方忠强李佳文毛建军王桢杨帆席航何文
Owner NUCLEAR POWER INSTITUTE OF CHINA