Test device for simulating nuclear reactor fuel rod

A nuclear reactor fuel and test device technology, applied in the field of simulation tests, can solve problems such as cladding tube bending deformation, nuclear safety threats, brittle fractures, etc., and achieve the effects of avoiding leakage, ensuring test safety, and satisfying gas pressure

Active Publication Date: 2021-02-19
STATE POWER INVESTMENT CORP RES INST
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At the same time, the cladding tube also produces large axial stress under the action of swelling deformation, transient thermal stress, etc., and the cladding tube undergoes bending deformation, swelling, brittle fracture or blasting, which poses a serious threat to nuclear safety.

Method used

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  • Test device for simulating nuclear reactor fuel rod
  • Test device for simulating nuclear reactor fuel rod
  • Test device for simulating nuclear reactor fuel rod

Examples

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Embodiment Construction

[0023] Embodiments of the invention are described in detail below, examples of which are illustrated in the accompanying drawings. The embodiments described below by referring to the figures are exemplary and are intended to explain the present invention and should not be construed as limiting the present invention.

[0024] Such as Figure 1-Figure 4 As shown, a test device 001 for simulating a nuclear reactor fuel rod according to an embodiment of the present invention includes a cladding tube 100 , an insulating tube 200 and a heating tube 300 .

[0025] Such as figure 1 As shown, gas is passed into the heating tube 300, and the heating tube 300 is suitable for connecting to an external power supply device through a first wire and a second wire. The cladding tube 100 is sleeved on the insulating tube 200 , and the inner peripheral surface of the cladding tube 100 is in contact with the outer peripheral surface of the insulating tube 200 . The insulating tube 200 is sleev...

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PUM

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Abstract

The invention discloses a test device for simulating a nuclear reactor fuel rod. The test device for simulating a nuclear reactor fuel rod comprises a cladding pipe, an insulating pipe and a heating pipe. The cladding pipe sleeves the insulating pipe, and the inner circumferential surface of the cladding pipe is in contact with the outer circumferential surface of the insulating pipe. The heatingpipe is sleeved with the insulating pipe, and the inner circumferential surface of the insulating pipe makes contact with the outer circumferential surface of the heating pipe. The heating pipe is provided with a heating cavity, the heating pipe is provided with a gas channel communicated with the heating cavity, the gas channel penetrates through the heating pipe in the radial direction of the heating pipe, one end of the heating cavity is closed, the other end of the heating cavity is suitable for being communicated with an air source, and the heating pipe is suitable for being connected with external power supply equipment through a first wire and a second wire. The test device for simulating a nuclear reactor fuel rod can utilize electric heating to simulate the performance of a fuel rod to carry out a pressurization simulation test.

Description

technical field [0001] The invention relates to the technical field of simulation tests, in particular to a test device for simulating nuclear reactor fuel rods. Background technique [0002] Under the accident conditions of the PWR nuclear power plant, the fuel rods in the cladding tube expand rapidly, and the fission gas generates a large internal pressure in the tube. At the same time, the cladding tube also produces large axial stress under the action of swelling deformation and transient thermal stress, and the cladding tube undergoes bending deformation, swelling, brittle fracture or blasting, which poses a serious threat to nuclear safety. [0003] In order to carry out the pressure test on the cladding tube under accident conditions, a test device simulating the fuel core rod in the cladding tube is needed. Contents of the invention [0004] The present invention aims to solve one of the technical problems in the related art at least to a certain extent. [0005]...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 汪峰李怀林兰雪影
Owner STATE POWER INVESTMENT CORP RES INST
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