Passive high-temperature heat pipe fast reactor core heat transfer system and method

A high-temperature heat pipe and heat transfer system technology, applied in the field of passive high-temperature heat pipe fast reactor core heat transfer system, can solve problems such as corrosion of structural component materials, increased safety hazards of fast reactor nuclear power plants, threats to reactor safety operation, etc., to improve safety Performance, small charge effect

Inactive Publication Date: 2017-01-04
SOUTH CHINA UNIV OF TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, these two coolants also have fatal shortcomings
Among them, the sodium coolant and the lead coolant are easy to chemically react with air and water, which poses a huge threat to the safe operation of the reactor; while the lead-bismuth coolant corrodes the materials of the structural components quite seriously at the operating temperature
In addition, the current pump power cycle heat conduction system also increases the safety hazards of fast reactor nuclear power plants

Method used

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  • Passive high-temperature heat pipe fast reactor core heat transfer system and method
  • Passive high-temperature heat pipe fast reactor core heat transfer system and method

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Embodiment

[0020] Such as figure 1 , 2 shown. The invention discloses a passive high-temperature heat pipe fast reactor core heat transfer system, which includes a fast reactor coolant pool 7 filled with sodium liquid, a heat pipe 2 and a steam generator 1; the lower end of the heat pipe 2 is placed in the fast reactor for cooling In the sodium liquid of the agent pool 7, the upper end of the heat pipe 2 is placed in the water of the steam generator 1.

[0021] The reactor fuel assembly 3 is placed in the fast reactor coolant pool 7, and the reactor fuel assembly 3 is submerged under the liquid surface of the sodium liquid.

[0022] The heat pipe 2 is a plurality of vertical heat pipe arrays arranged parallel to each other at intervals; the steam generator 1 is located above the fast reactor coolant pool 7 .

[0023] The bottom side wall of the steam generator is provided with a high-pressure water inlet 6, and the top is provided with a steam outlet 4; the reactor fuel assembly 3 emi...

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Abstract

The invention discloses a passive high-temperature heat pipe fast reactor core heat transfer system and method. The system comprises a fast reactor cooling agent pond containing sodium liquid, heat tubes and a steam evaporator. The lower ends of the heat tubes are placed in the sodium liquid of the fast reactor cooling agent pond, and the upper ends of the heat tubes are placed in water of the steam generator. A reactor fuel assembly is placed in the fast reactor cooling agent pond and immersed under the liquid surface of the sodium liquid. A sodium cooling agent and a reactor core fuel assembly are sealed, heat transfer is conducted on the steam evaporator through the heat tubes, the heat tubes can be filled with mercury, lead, bismuth, tin and other alloy which can not chemically react with water easily and serve as working media, the sodium cooling agent cannot transfer heat directly with water, and safety is greatly improved. Mercury serves as the working medium of the heat tubes, and due to the fact that the charging amount of single heat tubes is small, direct security threats are not caused even if the heat tubes leak.

Description

technical field [0001] The invention relates to a heat transfer component and a process, in particular to a passive high temperature heat pipe fast reactor core heat transfer system and a method thereof. Background technique [0002] At present, the utilization rate of natural uranium resources in pressurized water reactors (such as Qinshan and Daya Bay nuclear power plants in my country) widely used in nuclear power plants is only about 1%, while fast reactors can increase this utilization rate to 60%-70% %. This is of great significance for making full use of uranium resources, promoting the sustainable development of nuclear power, and solving subsequent energy supply problems. Relatively lean uranium deposits have also gained mining value due to increased utilization. Worldwide, this would increase the resources of recoverable uranium by a thousandfold. [0003] To prevent neutron moderation, substances containing hydrogen nuclei cannot be used in fast reactors, so wat...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/06G21C15/14
CPCG21C15/06G21C15/14Y02E30/30
Inventor 许雄文刘金平潘垚池
Owner SOUTH CHINA UNIV OF TECH
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