A flow channel adjustment system for vibration resistance tests of nuclear reactor components

Abstract

An embodiment of the present invention relates to a flow channel adjustment system for vibration resistance tests of nuclear reactor components, including: a vibration resistance test module, and a flow channel adjustment module provided on the vibration resistance test module. The vibration resistance test module includes a single nuclear reactor component, and the flow channel adjustment module adjusts the size between the reactor component in the vibration resistance test module and the flow channel adjustment plate through a spiral adjustment knob. The flow channel adjustment system for vibration resistance tests of nuclear reactor components provided by the embodiments of the present application can adjust the flow channel size of the reaction components in the vibration resistance test module by providing a flow channel adjustment module on the vibration resistance test module. The flow channel adjustment system for vibration resistance tests of nuclear reactor components provided by the embodiments of the present application can achieve a change in the size between the reactor component and the flow channel adjustment plate by designing the flow channel adjustment module, can meet the requirements of different reactors for different component clearances, and realizes structural diversification.

Description

Technical Field

[0001] The embodiments of the present invention relate to the technical field of vibration resistance testing, and in particular, to a flow channel adjustment system for vibration resistance testing of nuclear reactor components. Background Art

[0002] In a fast neutron nuclear reactor (fast reactor), hundreds of components (including fuel rod assemblies, shielding assemblies, control rod assemblies, etc.) are closely arranged on a grid. During operation, the components emit a large amount of nuclear energy (neutrons) due to nuclear reactions, heating the surrounding cooling medium. The cooling medium circulates driven by a circulation pump and thus obtains thermal energy.

[0003] The vibration generated during the operation of the circulation pump will be transmitted to the reactor components. To ensure the safety of the long-term operation of the nuclear reactor, it is necessary to conduct vibration resistance tests on various types of components in advance. The vibration resistance test needs to consider the influence of the fluid environment on the dynamic characteristics of the structure: the main factors are the density and viscosity of the fluid, and the flow channel configuration formed between components. Mechanical analysis shows that the flow channel size between components has a significant additional influence on the vibration of components, which is one of the main factors that cannot be ignored in the test. Summary of the Invention

[0004] In order to solve the above technical problems or at least partially solve the above technical problems, the present application provides a flow channel adjustment system for vibration resistance testing of nuclear reactor components.

[0005] The embodiments of the present application provide a flow channel adjustment system for vibration resistance testing of nuclear reactor components, including: a vibration resistance test module, and a flow channel adjustment module provided on the vibration resistance test module. The vibration resistance test module includes a single nuclear reactor component, and the flow channel adjustment module adjusts the size between the reactor component in the vibration resistance test module and the flow channel adjustment plate through a spiral adjustment knob.

[0006] In a possible implementation manner, the vibration resistance test module includes: a test sleeve and a support flange. The test sleeve is connected to the support flange through a plurality of reinforcing ribs to ensure the natural frequency of the vibration resistance test module. The test sleeve is provided with a plurality of fixed pitches and circumferentially arranged openings.

[0007] In a possible implementation manner, the flow channel adjustment module includes: a flow channel adjustment plate, a spiral adjustment knob, and an adjustment column;

[0008] The flow channel adjustment plate is placed on the inner wall of the test sleeve and is used to be close to the components inside the test sleeve. The flow channel adjustment plate is fixedly connected to the adjustment column. The adjustment column extends out of the opening, and the spiral adjustment knob is connected to one end of the adjustment column extending out of the opening.

[0009] In a possible implementation, the adjusting column and the spiral adjusting knob are provided with matching threads. By rotating the spiral adjusting knob on the adjusting column, the size between the reactor assembly and the flow channel adjusting plate in the vibration-resistant test module can be adjusted.

[0010] The above technical solutions provided by the embodiments of the present application have the following advantages compared with the prior art: The embodiments of the present application provide a flow channel adjusting system for the vibration-resistant test of nuclear reactor assemblies. By designing the flow channel adjusting module, the size between the reactor assembly and the flow channel adjusting plate can be changed, which can meet the requirements of different reactors with different component clearances and achieve structural diversification. BRIEF DESCRIPTION OF THE DRAWINGS

[0011] The accompanying drawings herein are incorporated into the specification and form a part of the specification, showing embodiments consistent with the present invention and, together with the specification, are used to explain the principles of the present invention.

[0012] In order to more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the following will briefly introduce the drawings required for use in the description of the embodiments or the prior art. Obviously, for those of ordinary skill in the art, without creative efforts, other drawings can also be obtained based on these drawings.

[0013] Figure 1 It is an assembly schematic diagram of a flow channel adjusting system for the vibration-resistant test of nuclear reactor assemblies provided by the embodiments of the present application;

[0014] Figure 2 It is a structural schematic diagram of a flow channel adjusting system for the vibration-resistant test of nuclear reactor assemblies provided by the embodiments of the present application;

[0015] Figure 3 It is a schematic diagram of a flow channel adjusting module provided by the embodiments of the present application;

[0016] Figure 4 It is a schematic diagram of a flow channel adjusting module provided by the embodiments of the present application. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0017] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the following will clearly and completely describe the technical methods in the embodiments of the present invention with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are only a part of the embodiments of the present invention, rather than all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those of ordinary skill in the art without creative efforts fall within the protection scope of the present invention.

[0018] It should be noted that if there are directional indications (such as up, down, left, right, front, back, etc.) involved in the embodiments of the present invention, the directional indications are only used to explain the relative positional relationship and motion conditions between components in a specific posture. If the specific posture changes, the directional indications will also change accordingly.

[0019] The embodiment of the present application provides a flow channel adjustment system for the vibration resistance test of nuclear reactor components. Figure 1 As shown in the schematic diagram of a flow channel adjustment system for the vibration resistance test of nuclear reactor components provided by the embodiment of the present application, Figure 1 As shown, the adjustment system includes multiple vibration resistance test modules, and the flow channel adjustment modules on the vibration resistance test modules are arranged in an up-and-down mirror image. Specifically, as Figure 2 As shown, the flow channel adjustment system includes: a vibration resistance test module, and a flow channel adjustment module arranged on the vibration resistance test module. The vibration resistance test module includes a single nuclear reactor component 30, and the flow channel adjustment module adjusts the size between the reactor component and the flow channel adjustment plate 201 in the vibration resistance test module through a screw adjustment knob 202.

[0020] In the embodiment of the present application, as Figure 1 As shown, the vibration resistance test module includes: a test sleeve 101 and a support flange 102. The test sleeve 101 is connected to the support flange 102 through multiple reinforcing ribs 104 to ensure the natural frequency of the vibration resistance test module. As Figure 2 As shown, the test sleeve 101 is provided with multiple fixed pitches and circumferentially arranged openings 103. There are reinforcing ribs between the test sleeve and the support flange to increase the structural stiffness, so as to ensure that the natural frequency of the tooling does not affect the test process, and at the same time ensure the reliability of long-term vibration resistance.

[0021] In the embodiment of the present application, as Figure 2 As shown, the flow channel adjustment module includes: a flow channel adjustment plate 201, a screw adjustment knob 202, and an adjustment column 203; the flow channel adjustment plate 201 is placed on the inner wall of the test sleeve 101 and is used to be close to the components inside the test sleeve. The flow channel adjustment plate 201 is fixedly connected to the adjustment column 203. The adjustment column 203 extends out of the opening, and a screw adjustment knob 202 is connected to the end of the adjustment column 203 extending out of the opening.

[0022] It should be noted that the function of the adjustment plate is to maintain the flow channel configuration. Therefore, in the design, its deformation during the test should be minimized as much as possible, that is, through material selection and structural topology design, the first natural frequency of the overall structure of the adjustment plate and the stud is higher than the first natural frequency of the component. For example, the first natural frequency of a certain type of reactor component is about 17 Hz. Therefore, a local reinforcing rib structure can be designed for the adjustment plate to reduce the structural mass while increasing the structural stiffness. Or using composite materials such as carbon fiber can achieve the same effect.

[0023] In the embodiment of the present application, the adjusting column 203 and the screw adjusting knob 202 are provided with matching threads. By rotating the screw adjusting knob 202 on the adjusting column 203, the size between the reactor assembly and the flow channel adjusting plate 201 in the vibration-resistant test module can be adjusted. Specifically, as Figure 3 and Figure 4 shown, by rotating the screw adjusting knob on the adjusting column, the size between the reactor assembly and the flow channel adjusting plate can be increased / decreased. The adjustment steps include: installing the complete overall test tooling; adjusting the knob clockwise until the adjusting plate closely fits the outer wall of the test piece (assembly); adjusting the knob counterclockwise to an appropriate angle. For example, for a tooling with a pitch of 1 mm, every time it rotates 360 degrees, the adjusting plate retreats 1 mm; fix the knob after the adjustment is completed.

[0024] The embodiment of the present application provides a flow channel adjusting system for the vibration-resistant test of nuclear reactor assemblies. By designing the flow channel adjusting module, the size between the reactor assembly and the flow channel adjusting plate 201 can be changed, which can meet the requirements of different reactors with different component clearances and realizes the diversification of the structure.

[0025] The specific embodiments of the invention have been described in detail above. However, as an example, the invention is not limited to the specific embodiments described above. For those skilled in the art, any equivalent modification or substitution of the invention is also within the scope of the invention. Therefore, all equivalent transformations, modifications, improvements, etc. made without departing from the spirit and principle of the invention should be covered by the scope of the invention.

Claims

1. A flow channel adjustment system for vibration resistance test of nuclear reactor components, characterized in that, Comprising: A vibration-resistant test module, and a flow path adjustment module provided on the vibration-resistant test module. The vibration-resistant test module includes a single nuclear reactor assembly. The flow path adjustment module adjusts the size between the reactor assembly and the flow path adjustment plate in the vibration-resistant test module through a spiral adjustment knob. The vibration-resistant test module includes a test sleeve, and a plurality of circumferentially arranged openings are provided on the test sleeve. Wherein, the flow path adjustment module includes: a flow path adjustment plate, a spiral adjustment knob, and an adjustment column. The flow path adjustment plate is placed on the inner wall of the test sleeve and is used to be close to the components inside the test sleeve. The flow path adjustment plate is fixedly connected to the adjustment column. The adjustment column extends out of the opening, and one end of the adjustment column extending out of the opening is connected to the spiral adjustment knob.

2. The system according to claim 1, wherein The vibration-resistant test module further includes a support flange. The test sleeve is connected to the support flange through a plurality of reinforcing ribs to increase the natural frequency of the vibration-resistant test module. The plurality of openings on the test sleeve have a fixed pitch.

3. The system according to claim 2, wherein The adjustment column and the spiral adjustment knob are provided with matching threads. By rotating the spiral adjustment knob on the adjustment column, the size between the reactor assembly and the flow path adjustment plate in the vibration-resistant test module can be adjusted.

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