CN219591132U - Nuclear fuel cladding high-temperature steam oxidation test device - Google Patents
Nuclear fuel cladding high-temperature steam oxidation test device Download PDFInfo
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- CN219591132U CN219591132U CN202222963067.8U CN202222963067U CN219591132U CN 219591132 U CN219591132 U CN 219591132U CN 202222963067 U CN202222963067 U CN 202222963067U CN 219591132 U CN219591132 U CN 219591132U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model relates to a nuclear fuel cladding high-temperature steam oxidation test device which comprises a sample loading structure, wherein the sample loading structure comprises a placement component and a collecting piece arranged below the placement component, a test sample is a cylindrical sample, the placement component is used for the test sample to be placed in a standing manner, the placement component is of a ventilation structure, a gap is reserved between the outer wall surface of the test sample and the side surface of the placement component, the inner side of the test sample is communicated with the outside through the bottom of the placement component, so that high-temperature steam passes through the placement component when the high-temperature steam oxidation test is carried out, the inner side and the outer wall surface of the test sample are oxidized, and the collecting piece is used for collecting falling pieces of the test sample when the test is carried out. The nuclear fuel cladding high-temperature steam oxidation test device can ensure that a test sample can fully contact steam when the test sample is tested, and can ensure that the test sample stays in the test device, so that the test is more accurate.
Description
Technical Field
The utility model relates to the field of nuclear fuel protection, in particular to a nuclear fuel cladding high-temperature steam oxidation test device.
Background
A loss of coolant accident (LOCA, loss Of Coolant Accident) refers to an accident caused by loss of coolant in the primary loop of a nuclear reactor. When LOCA accident occurs, the reactor fuel rod cladding material undergoes severe chemical reaction in a high-temperature steam environment to cause the damage of the fuel rod cladding, thereby greatly threatening the safe operation of the reactor. Therefore, tests on the oxidation resistance and chemical behavior of the fuel rod cladding material in a high-temperature steam environment are required, and further, the cladding material is evaluated and improved, so that the safe operation of the nuclear reactor is ensured.
High temperature steam oxidation tests on fuel rod cladding materials typically use cylindrical samples, employing a double sided oxidation protocol. When the test is carried out, the sample is hung in a high-temperature steam environment, the part for hanging the cylindrical sample is called a hanger or a sample loading device, the part can bear the high temperature and oxidation effect in the high-temperature steam environment, and the full contact between the cylindrical sample and the high-temperature steam is ensured, so that the test is carried out smoothly, and the test result is accurate and reasonable, so that the adoption of a proper sample loading device is very important.
When the existing sample loading device is used for testing, high-temperature steam sweeps the sample upwards from the bottom, because the cylindrical sample is located on the tray, steam cannot smoothly enter the inner surface of the cylindrical sample due to the fact that the steam cannot pass through the tray, steam environments of the inner surface and the outer surface of the sample are possibly caused to be different, the inner surface of the sample cannot be fully oxidized, when the steam flow rate is large, steam conditions received by the inner surface and the outer surface of the sample are greatly different, and the high-temperature steam oxidation test is very likely to fail.
When the conventional other device is used for testing, although the inner surface and the outer surface of the cylindrical sample can be completely contacted with high-temperature steam, under certain high-temperature steam working conditions, the cylindrical sample is severely oxidized and cracked and can fall off from the device, so that the test cannot be continuously carried out, and for the test for measuring weight gain in real time, the peeling phenomenon of the surface of the sample can cause inaccuracy of the measured weight gain curve, thereby causing test failure.
Disclosure of Invention
The utility model aims to solve the technical problem of providing a nuclear fuel cladding high-temperature steam oxidation test device aiming at the defects in the prior art.
The technical scheme adopted for solving the technical problems is as follows: the nuclear fuel cladding high-temperature steam oxidation test device comprises a sample loading structure, wherein the sample loading structure comprises a placing component and a collecting piece arranged below the placing component;
the test sample is a cylindrical sample, and the placing component is used for placing the test sample vertically;
the placing component is of a ventilation structure, a gap is reserved between the outer wall surface of the test sample and the side surface of the placing component, and the inner side of the test sample is communicated with the outside through the bottom of the placing component, so that when a high-temperature steam oxidation test is carried out, high-temperature steam passes through the placing component to oxidize the inner side and the outer wall surface of the test sample;
the collecting piece is used for collecting the falling-off piece of the test sample when the test is carried out.
In some embodiments, the placement assembly includes a base that supports the lower end of the test sample and allows the passage of gas.
In some embodiments, the base is mesh.
In some embodiments, the placement assembly further comprises a protective barrel removably disposed at an upper end of the base.
In some embodiments, the protective cylinder is mesh-shaped to allow high temperature steam to pass through.
In some embodiments, the protective cylinder diameter is greater than the test sample diameter to avoid contact of the protective cylinder with the outer wall surface of the test sample.
In some embodiments, the collection member comprises a collection tray for collecting the test sample remover.
In some embodiments, the collection tray is mesh-like to allow high temperature steam to pass through.
In some embodiments, the collection tray is mesh-like, with mesh apertures on the collection tray being smaller than the size of the test sample removal member to prevent the test sample removal member from passing through the collection tray.
In some embodiments, the test device further comprises a weight measurement structure coupled to the sample loading structure to measure a change in weight of the test sample within the sample loading structure as the test is performed.
The nuclear fuel cladding high-temperature steam oxidation test device has the following beneficial effects: the device ensures that the inner wall surface and the outer wall surface can be fully contacted with steam when the test sample is subjected to high-temperature steam oxidation, so that the test is more accurate, meanwhile, the test sample can not fall out of the test device in the test process, the measurement of the weight of the test sample is accurate before and after the test, and in addition, the device can also test round tube test samples with different lengths, so that the device has wider applicability.
Drawings
The utility model will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic illustration of a nuclear fuel clad high temperature steam oxidation test apparatus in accordance with an embodiment of the present utility model;
fig. 2 is a top view of a sample structure in an embodiment of the utility model.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present utility model, a detailed description of embodiments of the present utility model will be made with reference to the accompanying drawings.
Fig. 1 to 2 show a nuclear fuel cladding high temperature steam oxidation test apparatus according to some embodiments of the present utility model, which may be used for performing a high temperature steam oxidation test on a nuclear fuel cladding, wherein the apparatus includes a sample loading structure 1 and a weight measuring structure 2, the sample loading structure 1 and the weight measuring structure 2 are connected, specifically, the weight measuring structure 2 is connected to the sample loading structure 1 through a connecting piece 13 on the sample loading structure 1, a test sample is placed into the sample loading structure 1 to perform the high temperature steam oxidation test, the sample loading structure 1 is a material resistant to high temperature steam oxidation such as platinum, the sample loading structure 1 does not react with the test sample under the high temperature steam environment, the weight measuring structure 2 performs weight measurement on the sample loading structure 1 loaded with the test sample when performing the test, so as to measure the weight change of the test sample in the sample loading structure 1, and accordingly analyze the test result of the test sample.
The test sample is a cylindrical sample and is made of a nuclear fuel cladding material, and the nuclear fuel cladding material is damaged due to severe chemical reaction in a high-temperature steam environment, so that the safe operation of a reactor is greatly threatened, and therefore, the oxidation resistance and the chemical behavior of the nuclear fuel cladding material in the high-temperature steam environment are required to be tested, namely, the inner side and the outer wall surface of the test sample are required to be subjected to high-temperature steam oxidation tests, so that the cladding material for constructing the test sample is evaluated and improved, and the safe operation of the nuclear reactor is ensured.
Therefore, the device can ensure that the inner wall surface and the outer wall surface can be fully contacted with steam when the test sample is subjected to high-temperature steam oxidation, so that the test is more accurate, and meanwhile, the test sample can not fall out of the test device in the test process, and the measurement of the weight of the test sample is accurate before and after the test.
The sample loading structure 1 in some embodiments comprises a placing component 11 and a collecting piece 12, the placing component 11 is used for placing a test sample vertically, the test sample is subjected to high-temperature steam oxidation test in the placing component 11, the collecting piece 12 is installed below the placing component 11 and is used for collecting a falling piece of the test sample, namely an object falling off from the test sample, when the test sample is tested, partial samples fall off, the falling samples need to be collected, the test sample is prevented from falling out of the test device, because weight change of the test sample when the test sample is tested needs to be measured in real time through the weight change of the test sample is not accurate if the partial test sample falls out of the test device, test data has no reference value, and therefore the falling test sample needs to be collected, and the accuracy of the test is ensured.
Further, place the subassembly 11 for ventilative structure, when the test sample was placed in placing the subassembly 11, leave the space between the side of test sample outer wall surface and placing the subassembly 11, prevent to place the subassembly 11 and shelter from test sample outer wall surface, make high temperature steam and test sample outer wall surface complete contact, and then ensure the accuracy of test result, the test sample inboard communicates with the external world through the bottom of placing the subassembly 11, because place the subassembly 11 wholly for ventilative structure, so gaseous can pass the bottom of placing the subassembly 11 from the external world and contact with the inboard of test sample, thereby let the inboard of test sample oxidize, therefore when carrying out high temperature steam oxidation test, high temperature steam sweeps and places the subassembly 11 and pass and place the subassembly 11, contact and oxidize with test sample inboard and outer wall surface.
The placement module 11 in some embodiments includes a base 111 for supporting a test sample placed on the base 111 to allow the test sample to be tested within the placement module 11.
Further, the base 111 is of a mesh structure, so that when the placement component 11 is purged by high-temperature steam, the high-temperature steam passes through the base 111 to reach the inner side of the test sample, and the inner side is contacted with the high-temperature steam and oxidized.
The placement module 11 further comprises a protection barrel 112 in some embodiments, the protection barrel 112 is detachably arranged at the upper end of the base 111, the connecting piece 13 is arranged at the upper end of the protection barrel 112, the height of the protection barrel 112 is larger than the axial length of the test sample and is used for providing support for the test sample, meanwhile, the test sample is prevented from falling out of the placement module 11, in addition, the height of the protection barrel 112 can be adjusted according to the axial length of the test sample and the condition of high-temperature steam, so that the device can test round tube test samples with different lengths, and has wider applicability.
Further, the protection cylinder 112 has a net structure, and when the placement component 11 is purged by high-temperature steam, the high-temperature steam passes through the net of the protection cylinder 112 to contact with the outer wall surface of the test sample, so that the outer wall surface of the test sample is oxidized.
In other embodiments, the protection cylinder 112 is a frame structure, and is circumferentially arranged along the upper end of the base 111, and the frame has a larger lattice than the mesh of the mesh structure, which is more beneficial for passing high-temperature steam compared with the mesh structure, and meanwhile, the protection cylinder 112 can further save materials by adopting the lattice, and can save manufacturing cost by reducing the weight of the placement assembly 11.
Further, the diameter of the protection cylinder 112 is larger than that of the test sample, so that a certain gap is reserved between the outer wall surface of the test sample and the protection cylinder 112, the protection cylinder 112 is not in direct contact with the outer wall surface of the test sample, if the protection cylinder 112 is in direct contact with the outer wall surface of the test sample, the contact surface cannot be purged by high-temperature steam, so that the parts cannot be oxidized, the experimental result is affected, and therefore, the protection cylinder 112 cannot be in direct contact with the outer wall surface of the test sample, and all the outer wall surfaces of the test sample can be contacted with the high-temperature steam and oxidized, so that the accuracy of the experimental result is improved.
The collection member 12 in some embodiments comprises a collection tray 121, the collection tray 121 being mounted below the placement module 11, in particular, the collection tray 121 being mounted below the base 111 for collecting objects falling off from the test sample, since there are some samples falling off when the test sample is tested, and the collection of these falling off samples is required to ensure the accuracy of the test.
Further, the collecting tray 121 is mesh-shaped, and the mesh aperture of the collecting tray 121 is smaller than the size of the falling-off piece of the test sample, so that the high-temperature steam can pass through the collecting tray 121 to contact the test sample, and the falling-off piece of the test sample can not fall out of the collecting tray 121, so that the accuracy of the test is ensured, specifically, when the high-temperature steam sweeps the sample loading structure 1, the high-temperature steam passes through the collecting tray 121 first and then passes through the base 111 and the protection cylinder 112 again, finally contacts the outer wall surface and the inner side of the test sample, so that the outer wall surface and the inner side of the test sample are oxidized, and the inner side and the outer wall surface of the test sample can fall off when oxidized, and the falling-off piece can fall onto the collecting tray 121, but the mesh aperture of the collecting tray 121 is smaller than the size of the falling-off piece, so that the sample can stay on the collecting tray 121 instead of falling off the collecting tray 121, so that the accuracy of the test result is ensured.
When the device is used for testing, firstly, a test sample is placed in a sample loading structure 1, then the sample loading structure 1 is connected with a weight measuring structure 2, then the sample loading structure 1 starts to be purged by high-temperature steam, the high-temperature steam passes through a protection cylinder 112 of a placement component 11 and then contacts with the outer wall surface of the test sample, the outer wall surface is oxidized, the high-temperature steam passes through a base 111 of the placement component 11 and then contacts with the inner side of the test sample, the inner side is oxidized, then partial samples fall off in the oxidation process of the outer wall surface and the inner side of the test sample, then the falling parts fall on a collecting disc 121 and are collected by the collecting disc 121, at the moment, the weight measuring structure 2 measures the weight of the sample loading structure 1 in real time, the weight change of the test sample in the sample loading structure 1 is measured, and the weight change of the test sample in a period of time is analyzed, so that a test result can be obtained.
It will be appreciated that the above technical features may be used in any combination without limitation.
The foregoing is only illustrative of the present utility model and is not to be construed as limiting the scope of the utility model, and all equivalent structures or equivalent flow modifications which may be made by the teachings of the present utility model and the accompanying drawings or which may be directly or indirectly employed in other related art are within the scope of the utility model.
Claims (10)
1. The nuclear fuel cladding high-temperature steam oxidation test device is characterized by comprising a sample loading structure (1), wherein the sample loading structure (1) comprises a placement component (11) and a collecting piece (12) arranged below the placement component (11);
the test sample is a cylindrical sample, and the placing component (11) is used for placing the test sample vertically;
the placing component (11) is of a ventilation structure, a gap is reserved between the outer wall surface of the test sample and the side surface of the placing component (11), the inner side of the test sample is communicated with the outside through the bottom of the placing component (11), so that when a high-temperature steam oxidation test is carried out, high-temperature steam passes through the placing component (11) to oxidize the inner side and the outer wall surface of the test sample;
the collecting piece (12) is used for collecting falling pieces of test samples when the test is carried out.
2. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 1, wherein the placement assembly (11) comprises a base (111) supporting the lower end of the test sample and allowing gas to pass therethrough.
3. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 2, wherein the base (111) is mesh-like.
4. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 2, wherein the placement assembly (11) further comprises a protective barrel (112) detachably disposed at an upper end of the base (111).
5. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 4, wherein the protective cylinder (112) is mesh-shaped to allow high temperature steam to pass through.
6. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 5, wherein the protective cylinder (112) has a diameter greater than the test sample diameter to avoid contact of the protective cylinder (112) with an outer wall surface of the test sample.
7. The nuclear fuel cladding high temperature steam oxidation test device of claim 1, wherein the collection member (12) comprises a collection tray (121) for collecting test sample shedding members.
8. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 7, wherein the collection tray (121) is mesh-shaped to allow high temperature steam to pass through.
9. The nuclear fuel cladding high temperature steam oxidation test apparatus of claim 8, wherein the collection tray (121) is mesh-like, and mesh apertures on the collection tray (121) are smaller than the size of the test sample stripping member to avoid the test sample stripping member from passing through the collection tray (121).
10. The nuclear fuel cladding high temperature steam oxidation test device according to any one of claims 1 to 9, further comprising a weight measurement structure (2), the weight measurement structure (2) being connected to the sample loading structure (1) to measure weight change of a test sample within the sample loading structure (1) when the test is performed.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202222963067.8U CN219591132U (en) | 2022-11-03 | 2022-11-03 | Nuclear fuel cladding high-temperature steam oxidation test device |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202222963067.8U CN219591132U (en) | 2022-11-03 | 2022-11-03 | Nuclear fuel cladding high-temperature steam oxidation test device |
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| Publication Number | Publication Date |
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| CN219591132U true CN219591132U (en) | 2023-08-25 |
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| CN202222963067.8U Active CN219591132U (en) | 2022-11-03 | 2022-11-03 | Nuclear fuel cladding high-temperature steam oxidation test device |
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| CN (1) | CN219591132U (en) |
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- 2022-11-03 CN CN202222963067.8U patent/CN219591132U/en active Active
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