Detection, storage and transfer system based on nuclear fuel graphite sample test

Abstract

The invention relates to a detection, storage and transfer system based on nuclear fuel graphite sample testing, which comprises a first detection system, a second detection system, a sample connection table, an AGV (Automatic Guided Vehicle) conveying trolley, a graphite carrier, a first intelligent bin and a second intelligent bin, the first detection system comprises a graphite powder apparent density detection machine, a falling ball test device, a crushing load test device, an abrasion test device, a graphite ball density detection device, a corrosion test device, a thermal analysis test device, an equivalent weight detection device, a uranium pollution rate and Li content detection device and the like; and the second detection system comprises a pneumatic transmission device, a coating detection device, a loose layer density detection device, a core detection device, a central control analysis detection device and a particle density detection device. The device has the beneficial effects that the device can adapt to automatic storage and transfer of graphite samples in two forms of spheres and powder particles to each detection device for detection, and the detection efficiency, wall surface repeated detection and missing detection of the graphite samples are improved.

Description

Technical Field

[0001] The invention relates to the field of detection material flow systems, and in particular to a detection storage and transportation system based on nuclear fuel graphite sample testing. Background Art

[0002] Nuclear fuel graphite balls are key materials for building new generation nuclear power plants such as high temperature gas-cooled reactors and fast reactors. Nuclear-grade graphite powder is the base material of spherical fuel elements. The spherical fuel elements of high temperature gas-cooled reactors are composed of a fuel zone and a fuel-free zone, with a diameter of 60 mm. The fuel zone is a sphere with a diameter of about 50 mm in which the coated fuel particles are dispersed in the graphite matrix. The fuel-free zone is a graphite shell with a thickness of about 5 mm outside the fuel zone. The coated fuel particles are TRISO-type, with a ceramic uranium dioxide core in the center, and the outer layers are loose pyrolytic carbon layer, inner dense pyrolytic carbon layer, silicon carbide layer and outer dense pyrolytic carbon layer from the inside to the outside.

[0003] After production, nuclear fuel graphite ball samples need to be tested by a variety of testing devices to obtain the physical and chemical properties data of the graphite samples. Since there are many types of graphite samples in the testing process, different types of samples undergo different testing procedures. The existing sample flow is carried out in the form of manual feeding, which not only reduces the detection efficiency, but also is prone to missed detection and re-inspection. Therefore, a detection storage and transportation system based on nuclear fuel graphite sample testing is needed. Summary of the invention

[0004] The purpose of the present invention is to provide a detection storage and transportation system based on nuclear fuel graphite sample testing, which can adapt to the automated storage and transfer of various types of graphite samples to various detection devices for detection, thereby improving the detection efficiency of graphite samples and preventing repeated wall detection and missed detection.

[0005] In order to achieve the above-mentioned purpose, the present invention provides the following technical solutions: a detection storage and transportation system based on nuclear fuel graphite sample testing, comprising a first detection system, a second detection system, a sample docking station, an AGV conveyor trolley, a graphite carrier, a first intelligent warehouse and a second intelligent warehouse, wherein the first detection system comprises a graphite powder loose density detection machine, a drop ball test device, a crushing load test device, a wear test device, a graphite ball density detection device, a corrosion test device, a thermal analysis test device, an equivalent detection device, a uranium contamination rate and Li content detection device, a surface uranium detection device, and a graphite ball damage detection device. The graphite carrier is transported and circulated by the AGV in the first detection system, in the second detection system, between the first intelligent warehouse and the sample docking station and the first detection system, and between the second intelligent warehouse and the sample docking station and the second detection system.

[0006] Furthermore, a manipulator is fixedly connected to the side of the tray of the AGV vehicle.

[0007] Furthermore, the graphite carrier includes a seat plate, and a plurality of positioning cylinders are fixedly connected to the seat plate.

[0008] Furthermore, a plurality of the positioning tubes are distributed in an array on the seat plate.

[0009] Furthermore, the sample docking station includes a base and a plurality of racks fixed on the base, and the racks are multi-layer racks.

[0010] Furthermore, each of the multi-layer material racks is fixedly connected with a positioning block.

[0011] The beneficial effects of the present invention are: it can adapt to the automated storage and transfer of various types of graphite samples to various detection devices for detection, thereby improving the detection efficiency of graphite samples and the repeated detection and missed detection of wall surfaces. BRIEF DESCRIPTION OF THE DRAWINGS

[0012] Figure 1 It is a schematic diagram of the first detection system of the present invention.

[0013] Figure 2 It is a schematic diagram of a second detection system of the present invention.

[0014] Figure 3 This is the AGV calling flow chart of the present invention. DETAILED DESCRIPTION

[0015] In order to make the purpose, technical solution and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not used to limit the present invention.

[0016] refer to Figure 1-Figure 3 The test storage and transportation system based on nuclear fuel graphite sample testing shown in the figure includes a first detection system, a second detection system, a sample docking station, an AGV conveyor trolley, a graphite carrier, a first intelligent warehouse and a second intelligent warehouse, wherein the first detection system includes a graphite powder loose density detection machine, a drop ball test device, a crushing load test device, a wear test device, a graphite ball density detection device, a corrosion test device, a thermal analysis test device, an equivalent detection device, a uranium contamination rate and Li content detection device, a surface uranium detection device, a graphite ball damage detection device, and a free uranium detection device. The graphite carrier is transported and circulated by the AGV in the first detection system, in the second detection system, between the first intelligent warehouse and the sample docking station and the first detection system, and between the second intelligent warehouse and the sample docking station and the second detection system.

[0017] A manipulator is fixedly connected to the side of the tray of the AGV trolley, and the manipulator is used to load and unload the graphite carrier.

[0018] The graphite carrier comprises a base plate, on which a plurality of positioning tubes are fixedly connected, and the positioning tubes can adapt to the positioning and storage of graphite samples in two forms.

[0019] A plurality of the positioning cylinders are distributed in an array on the seat plate.

[0020] The sample docking station includes a base and a plurality of racks fixed on the base. The sample docking station can transfer and cache graphite carriers, and the racks are multi-layer racks.

[0021] A positioning block is fixedly connected to each of the multi-layer material racks, and the positioning block can limit the graphite carrier to prevent the graphite carrier from being misplaced.

[0022] The working principle of the present invention is as follows: when in use, the present invention detects graphite samples through the first detection system and the second detection system. The present invention loads different types of graphite samples through a graphite carrier. At the first detection system, the graphite samples are sampled from the graphite sampling point by an AGV trolley and transported to the first intelligent warehouse for classified storage. When performing the detection, the designated samples are called out through the first intelligent warehouse and sent to a graphite powder loose density detector, a drop ball test device, a crushing load test device, a wear test device, a graphite ball density detection device, a corrosion test device, a thermal analysis test device, an equivalent detection device, a uranium contamination rate and Li content detection device or a free uranium detection device for detection through the AGV trolley. After the graphite samples have completed the drop ball detection, crushing load test, wear test, density test, corrosion test, and thermal analysis test, they are transported to the receiving place of the first intelligent warehouse through the AGV, and the samples that have completed the detection are transported to the corresponding warehouse position through the sorting mechanism of the first intelligent warehouse. After the equivalent The tested samples are transferred from the equivalent detection device to the graphite ball weighing device for weighing by AGV. The weighed samples and the samples that have been tested for uranium contamination rate and Li content are transferred to the graphite ball roasting device and the graphite ball chemical treatment device for testing in turn. Finally, the samples are transferred to the sample docking station by AGV. The samples on the sample docking station are subsequently transferred to the surface uranium detection device and the graphite ball damage detection device for testing. The samples that have been tested by the surface uranium detection device are returned to the sample docking station. The samples that have passed the graphite ball damage detection device will be transported to the particle burning device and the particle chemical treatment device in turn by the AGV cart for testing and chemical treatment. The samples that have been tested and treated are transported to the sample docking station, where the corresponding samples can also be directly retrieved from the sample docking station to the particle weighing device for weighing and then sent to the particle chemical treatment device for processing. The samples that have been tested for free uranium are transferred to the graphite ball roasting device and the graphite ball chemical treatment device for testing by AGV in turn, and finally the samples are returned to the sample docking station.

[0023] At the second detection system, the graphite samples are sampled from the graphite sampling point by the AGV cart and transported to the second intelligent warehouse for classification and storage. After that, the samples are transferred from the discharge port of the second intelligent warehouse to the pneumatic transmission device and the sample docking station by the AGV. Then, the samples at the discharge end of the pneumatic transmission device are respectively transferred to the loose layer density detection device, the core detection device, the central control analysis detection device and the particle density detection device for detection by the AGV. The coating detection device is transferred from the sample docking station by the AGV. The various samples detected by the coating detection device, the loose layer density detection device, the core detection device, the central control analysis detection device and the particle density detection device are transported to the second intelligent warehouse for storage by the AGV. The samples that have completed the detection in the first intelligent warehouse and the second intelligent warehouse are transported to the sample withdrawal point.

[0024] In the present invention, unless otherwise clearly specified and limited, the terms "connected", "connected", "fixed" and the like should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection or an indirect connection through an intermediate medium, it can be the internal connection of two elements or the interaction relationship between two elements. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0025] The above embodiments are used to further illustrate the present invention, but the present invention is not limited to these specific embodiments. Any modification, equivalent substitution and improvement made within the spirit and principle of the present invention should be understood to be within the protection scope of the present invention.

Claims

1. A detection storage and transportation system based on nuclear fuel graphite sample testing, characterized in that: It includes a first detection system, a second detection system, a sample docking station, an AGV transport trolley, a graphite carrier, a first intelligent warehouse and a second intelligent warehouse. The first detection system includes a graphite powder loose density detector, a drop ball test device, a crushing load test device, a wear test device, a graphite ball density detection device, a corrosion test device, a thermal analysis test device, an equivalent detection device, a uranium contamination rate and Li content detection device, a surface uranium detection device, a graphite ball breakage detection device, a free uranium detection device, a graphite ball roasting device, a graphite ball weighing device, a particle burning device, a graphite ball chemical treatment device, a particle chemical treatment device and a particle weighing device. The second detection system includes a pneumatic transmission device, a coating detection device, a loose layer density detection device, a core detection device, a central control analysis detection device and a particle density detection device. The graphite carrier is transported and circulated by the AGV trolley in the first detection system, in the second detection system, between the first intelligent warehouse and the sample docking station and the first detection system, and between the second intelligent warehouse and the sample docking station and the second detection system.

2. The detection storage and transportation system based on nuclear fuel graphite sample testing according to claim 1 is characterized in that: A manipulator is fixedly connected to the side of the tray of the AGV trolley.

3. The detection storage and transportation system based on nuclear fuel graphite sample testing according to claim 1 is characterized in that: The graphite carrier comprises a seat plate, and a plurality of positioning cylinders are fixedly connected to the seat plate.

4. The detection storage and transportation system based on nuclear fuel graphite sample testing according to claim 1 is characterized in that: A plurality of the positioning cylinders are distributed in an array on the seat plate.

5. The detection storage and transportation system based on nuclear fuel graphite sample testing according to claim 1 is characterized in that: The sample docking station includes a base and a plurality of racks fixed on the base, and the racks are multi-layer racks.

6. The detection storage and transportation system based on nuclear fuel graphite sample testing according to claim 5 is characterized in that: A positioning block is fixedly connected on each of the multi-layer material racks.

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