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Bending stiffness test device and method for fast reactor components

A technology of bending stiffness and testing equipment, which is applied in the direction of measuring equipment, testing of machine/structural components, elastic testing, etc., to achieve the effect of eliminating inhomogeneity, ensuring the accuracy of experimental data, and large measuring range

Active Publication Date: 2019-02-26
XI AN JIAOTONG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

This device can apply horizontal loads to small specimens, but the fast reactor assembly is about 4 meters long, and the load needs to be applied at the upper and lower pads at a higher position, so this type of loading device cannot meet the requirements

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  • Bending stiffness test device and method for fast reactor components
  • Bending stiffness test device and method for fast reactor components
  • Bending stiffness test device and method for fast reactor components

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Embodiment Construction

[0044] The following specific examples illustrate the implementation of the present invention. Those skilled in the art can easily understand other advantages and effects of the present invention from the content disclosed in this specification.

[0045] Please participate Figure 1 to Figure 8 . It should be noted that the structure, ratio, size, etc. shown in the drawings of this specification are only used to match the content disclosed in the specification for people familiar with this technology to understand and read, and are not used to limit the implementation of the present invention. Any modification of the structure, modification of the proportional relationship or adjustment of the size should still fall within the scope covered by the technical content explained by the present invention without affecting the effects and goals that the present invention can produce. At the same time, the terms such as "big", "small", "up", "down", "left", "right", "middle", "inside", ...

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Abstract

The invention discloses a fast reactor assembly flexural rigidity test device and method. The device comprises fixedly installed stand columns. A top supporting platform and a middle supporting platform are arranged on the stand columns. The top supporting platform is provided with a large push rod base and a small push rod base. The middle supporting platform is provided with the small push rod base. The push rod bases are connected with horizontal loading devices. Each horizontal loading device comprises a servo motor, a push rod, a connecting flange, a tension-compression sensor, a C-shaped connector and a hexagonal hoop which are connected in turn through screws / bolts. The hexagonal hoop wraps the upper cushion block or the lower cushion block or the active area midplane of fast reactor assembly to apply horizontal push / pull force. The invention also provides the fast reactor assembly flexural rigidity test method. According to the fast reactor assembly flexural rigidity test device and method, the stress-deformation situation of the fast reactor assembly in the actual reactor can be simulated to the greatest extent so that the device and the method have the advantages of wide load range, uniform load distribution and high measurement accuracy.

Description

Technical field [0001] The invention belongs to the technical field of fast reactor component testing, and specifically relates to a fast reactor component flexural rigidity testing device and method. Background technique [0002] Sodium-cooled fast reactor components are the most important components in the reactor core. After the reactor is in operation, high temperature thermal expansion, coolant pressure difference, radiation brittleness, radiation swelling, radiation hardening, radiation creep, radiation fatigue, etc. Bending and deforming the components. Larger component deformations will adversely affect the safe operation of nuclear power plants, such as increased component insertion and removal forces, difficulty in component replacement, accelerated component damage, and inclination of core quadrant power. Obtaining the flexural rigidity of fast reactor components can verify the reliability of component material selection and structural design, on the other hand, it can...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01M5/00
CPCG01M5/005
Inventor 马泽华苏光辉巫英伟马振辉田文喜秋穗正
Owner XI AN JIAOTONG UNIV