Tangential fretting wear test fixture for nuclear power fuel cladding tube and grillwork rigid convex body

Abstract

The invention relates to the field of fretting wear, in particular to a tangential fretting wear test fixture for a nuclear power fuel cladding tube and a grillwork rigid convex body in high-temperature and high-pressure water, and a use method thereof. The tangential fretting wear test fixture mainly comprises a rigid convex body sample fixing block, a rigid convex body sample fastening stud, a rigid convex body sample fixing block clamp, a clamp fixing plate, a clamp fixing bracket, a cladding tube fixing base, an arc-shaped clamping block and the like. The use method comprises the steps of:embedding a rigid convex body test sample into a rigid convex body test sample fixing block; locking the rigid convex body sample by using the fastening stud; embedding the fixing block into a groovein the lower part of the rigid convex body sample fixing block clamp and fixing the same by means of a fastening screw; and then fixing the rigid convex body sample fixing block clamp on the clamp fixing plate and mounting the clamp fixing plate on the clamp fixing bracket, so that the fixation of the rigid convex body sample is realized. The tangential fretting wear test fixture is applied to tangential fretting wear tests of the pressurized water reactor nuclear power fuel cladding tube and the grillwork rigid convex body in the high-temperature and high-pressure primary loop water, and issimple in structure, convenient to operate and low in cost.

Description

technical field [0001] The invention relates to the field of fretting wear, in particular to a tangential fretting wear test fixture in high temperature and high pressure water for nuclear power fuel cladding tubes and lattice frames, and a method for using the same, which is used for pressurized water reactor nuclear power fuel cladding tubes and grids. Tangential fretting wear test of rigid convex body in high temperature and high pressure primary circuit water. Background technique [0002] In a pressurized water reactor, the fuel rod elements are held in the fuel assembly by friction between their cladding and the grid. When the reactor is operating, the coolant flows over the surface of the fuel rod cladding tube, causing the fuel rod to vibrate. This flow-induced vibration is one of the most important causes of fretting wear between the fuel rod cladding tube and the grid. The cladding tube located in the water of the primary circuit is the first important line of de...

AI Technical Summary

Problems solved by technology

In the laboratory simulating high temperature and high pressure primary circuit water, studying the fretting wear of the fuel cladding tube is an effective means to study the failure mechanism of the cladding tube, but the existing fixture design cannot meet the test requirements

First of all, the size of the rigid convex body and the fuel cladding tube is small, and it is difficult to clamp with conventional fixtures; secondly, the high-temperature and high-pressure water (200-360°C, 4-20MPa) environment is harsh, and the corrosion resistance of the fixture cannot be guaranteed

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