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Test bed for simulating thermal fatigue phenomenon of nuclear power station pipeline

A technology of test bench and thermal fatigue, which is applied in the direction of measuring devices, instruments, scientific instruments, etc., can solve the problems of not having a simulated nuclear power plant pipeline thermal fatigue test device, hindering the application research of nuclear power technology, and achieve the effect of deepening cognition

Active Publication Date: 2015-06-03
SUZHOU NUCLEAR POWER RES INST +1
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Problems solved by technology

[0003] However, in the prior art, there is no test device specially used to simulate the thermal fatigue phenomenon of nuclear power plant pipelines, which hinders the application research of nuclear power technology engineering

Method used

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  • Test bed for simulating thermal fatigue phenomenon of nuclear power station pipeline

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Embodiment Construction

[0026] Specific embodiments of the present invention will be described in detail below in conjunction with the accompanying drawings.

[0027] see figure 1 , The invention provides a test bench for simulating thermal fatigue phenomena of nuclear power plant pipelines, which includes a heating system, a cooling system, a T-shaped pipeline and a valve system, and a measurement and control system.

[0028] The heating system includes a thermal fluid storage tank 10, a high-level thermal fluid tank 11, a thermal fluid pump 12 that pumps the thermal fluid in the thermal fluid storage tank 10 into the high-level thermal fluid tank 11, and is located in the high-level thermal fluid tank 11 to measure heat. The first thermometer 13 for fluid temperature, the bottom of the high-level thermal fluid tank 11 is provided with a thermal fluid output pipeline 14, the thermal fluid output pipeline 14 is provided with a branch pipeline 15, and the thermal fluid storage tank 10 is provided with...

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Abstract

The invention provides a test bed for simulating the thermal fatigue phenomenon of a nuclear power station pipeline. The test bed comprises a heating system, a cooling system, a T-shaped pipeline and valve system, and a measurement and control system, wherein the heating system mainly comprises a fluid storage tank, a high-level thermal fluid tank, a thermal fluid pump and a first thermometer arranged in the high-level thermal fluid tank; the cooling system mainly comprises a clod fluid storage tank, a high-level cold fluid tank, a cold fluid pump and a second thermometer arranged in the high-level cold fluid tank; the T-shaped pipeline and valve system mainly comprises a three-way T-shaped pipe arranged horizontally, an upper electromagnetic valve and a lower electromagnetic valve; and the measurement and control system mainly comprises a first temperature controller, a second temperature controller, a first flowmeter and a second flowmeter, as well as a control acquisition system. The test bed provided by the invention is capable of simulating generation and development of the thermal fatigue phenomenon of the nuclear power station pipeline, and also capable of supporting the measurement and the estimation of the thermal fatigue phenomenon of the nuclear power station pipeline, and thereby advantageous for technical engineering application research.

Description

technical field [0001] The invention relates to a test bench, in particular to a test bench for simulating and studying thermal fatigue phenomena such as thermal stratification and thermal ripple caused by internal cooling of nuclear power plant pipelines and mixing of hot fluids. Background technique [0002] Material damage caused by cyclical thermal stress or thermal strain becomes thermal fatigue, also known as thermal stress fatigue. Thermal stress occurs when the free expansion or contraction of parts in service at high temperatures is restricted due to local temperature changes. Pipeline thermal fatigue is a phenomenon in which pipes are cracked or ruptured due to the long-term impact of alternating thermal stress. Although the probability of pipe ruptures caused by thermal fatigue is very small in nuclear power plants, pipe ruptures may cause accidents such as primary circuit breaks. , so it needs to be paid attention to. [0003] However, in the prior art, there i...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N3/02G01N3/60
Inventor 薛飞余伟炜蒙新明於旻遆文新张彦召罗志峰
Owner SUZHOU NUCLEAR POWER RES INST
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