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Prismatic gas cooled reactor thermal hydraulic comprehensive experiment loop system

An experimental circuit, thermal hydraulic technology, applied in reactors, nuclear engineering, nuclear reactor monitoring, etc.

Pending Publication Date: 2021-12-28
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, there is no test circuit suitable for prismatic type in the prior art. Therefore, it is necessary to provide a test circuit with reasonable design, simple structure and stable operation to meet the thermal hydraulic test requirements of prismatic gas-cooled reactors.

Method used

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  • Prismatic gas cooled reactor thermal hydraulic comprehensive experiment loop system

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Embodiment Construction

[0021] The present invention will be further described below in conjunction with specific embodiments and accompanying drawings.

[0022] figure 1 A schematic diagram of the working principle of the prismatic gas-cooled reactor thermal-hydraulic comprehensive experimental circuit system provided by the present invention is shown. The system includes a helium cylinder container 1, a vacuum pump 2, a buffer tank 3, a circulating fan 4, a mixer 5, Electric heating preheater 6, experimental section 7, heat exchanger 8, compressor 9, exhaust gas collection tank 10, loop pipeline and multiple valves.

[0023] The helium in the helium cylinder container 1 enters the circulation fan 4 through the loop pipe, and the helium flowing out of the circulation fan 4 is divided into two paths: the first path of gas is heated to the set inlet temperature through the electric preheater 6, and then It flows into the experimental section 7, and the experimental components inside the experimental ...

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Abstract

The invention relates to a prismatic gas cooled reactor thermal hydraulic comprehensive experiment loop system, and belongs to the field of nuclear technology, wherein helium in a helium tank container enters a circulating fan through a loop pipeline, the helium flowing out of the circulating fan is divided into two paths: the first path of gas is heated to a set inlet temperature through an electric preheater, and then flows into an experiment section; an experiment assembly in the experiment section heats the first path of gas to a set outlet temperature, and the first path of gas flows out of the experiment section and then enters a mixer; the second path of gas directly flows into the mixer after flowing out of the circulating fan, and the two paths of gas flow out after being mixed in the mixer, enter a heat exchanger for cooling and then flow into the circulating fan again. The experimental system provided by the invention can realize full-high, full-pressure and full-temperature simulation of key thermal hydraulic phenomena of a reactor core fuel assembly, a control rod assembly and a structural component, reveals a flow heat transfer mechanism and rule, and provides verification data for existing analysis and calculation.

Description

technical field [0001] The invention belongs to the field of nuclear technology, in particular to a prismatic air-cooled reactor thermal-hydraulic comprehensive experimental loop system. Background technique [0002] The research on thermal hydraulic characteristics of core fuel assemblies, control rod assemblies and structural components is of great significance to the safe operation of reactors and the design of related systems. In order to improve the performance and optimization of core fuel assemblies, control rod assemblies and structural components All countries have carried out thermal hydraulic analysis and experimental research on its design. [0003] Studies have shown that there are many factors affecting the thermal and hydraulic characteristics of the core fuel assembly, control rod assemblies and structural components, and the thermal parameters and structure of the system will have different effects on it. It is necessary to carry out experiments to test the ...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCG21C17/001Y02E30/30
Inventor 堵树宏张朔婷董建华张成龙朱思阳姚红孙燕宇杨长江贺楷刘国明陈巧艳汪俊
Owner CHINA NUCLEAR POWER ENG CO LTD
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