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Multi-loop natural circulation experiment device and method under six-degree-of-freedom motion condition

A technology of natural circulation and experimental device, used in measurement devices, fluid dynamics tests, engines using nuclear energy, etc., to reduce additional pressure drop and ensure cooling capacity.

Active Publication Date: 2021-06-01
XI AN JIAOTONG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] The purpose of the present invention is to provide a multi-loop natural circulation experiment under six-degree-of-freedom motion conditions in view of the fact that the above-mentioned experimental device or experimental system is not applicable or does not meet the needs of the nuclear engineering field for experimental research on the performance verification of nuclear power equipment under motion conditions. Device and method, the experimental device of the present invention can realize the motion of six degrees of freedom and the simulation of coupled motion; the relative position of the two cooling loops can be changed to realize the simulation of the natural circulation loop of different nuclear power systems; the heating can be changed according to the demand segment orientation to reduce the error caused by motion simulation

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  • Multi-loop natural circulation experiment device and method under six-degree-of-freedom motion condition

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Embodiment Construction

[0033] Below in conjunction with accompanying drawing and embodiment the present invention is described in detail:

[0034] Such as figure 1As shown, the multi-loop natural circulation experimental device under a six-degree-of-freedom motion condition of the present invention includes a six-degree-of-freedom motion simulation platform, a multi-loop main circulation loop, a cooling water system, and an electric heating system; the six-degree-of-freedom motion The simulation platform is composed of a mechanical platform, a drive system and a control system; the multi-loop main circulation loop includes a serpentine preheater 4, an experimental section 1, a pressurized circulation pump 7, a voltage stabilizer 6, an electromagnetic flowmeter 5, Exhaust valve 14, two casing condensers 15, wherein the serpentine preheater 4, the experimental section 1, and the pressurized circulation pump 7 are fixed on the mechanical platform of the six-degree-of-freedom motion simulation platform ...

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Abstract

The invention relates to a multi-loop natural circulation experiment device and method under a six-degree-of-freedom motion condition, and the device comprises a six-degree-of-freedom motion simulation platform, a multi-loop main circulation loop composed of a snakelike preheater, an experiment section, two sleeve type condensers, a pressurization circulation pump, a voltage stabilizer and related equipment, a cooling water system consisting of a double-pipe condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment, and an electric heating system consisting of a direct-current power supply, a low-voltage power controller and a transformer. The invention further provides an experimental method of the device. The device and method can meet the requirements of nuclear power system natural circulation loop characteristic experiment research with various different cooling loop arrangements under the condition of six-degree-of-freedom motion, and can effectively reduce the error of the experiment system under the condition of motion.

Description

technical field [0001] The invention belongs to the technical field of nuclear power equipment performance verification experiment research under motion conditions, and in particular relates to a multi-loop natural circulation experimental device and method under six-degree-of-freedom motion conditions. Background technique [0002] In nuclear reactors, natural circulation refers to the circulating flow caused by the density difference between the cold and hot fluids in the closed loop. Natural circulation can passively assist in the removal of residual heat from the core when the reactor is shut down, without providing any external driving force. Therefore, in the event of an accident such as a power outage in the entire plant, the reactor core can be effectively cooled to ensure the safety of the reactor core, which plays an important role in the safety of the reactor. [0003] Ships and nuclear power platforms at sea are affected by wind and waves, and the hull will prod...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01M10/00G21C17/00
CPCG01M10/00G21C17/001Y02E30/30B63H21/18Y02T70/50G21C17/022G21C17/112
Inventor 田文喜赖志贤王明军陈冲朱志明章静秋穗正苏光辉
Owner XI AN JIAOTONG UNIV
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