Experimental system for thermal-hydraulic characteristics and corrosive properties of liquid lead-bismuth alloy

A liquid lead-bismuth alloy, thermal hydraulic technology, applied in the field of nuclear energy, can solve the problems of inability to analyze and study the thermal hydraulic characteristics and corrosion characteristics of liquid lead-bismuth alloy, and the influence of liquid lead-bismuth oxygen concentration is large, and achieve the experimental temperature span The effect of large, precise temperature control and high operating temperature

Pending Publication Date: 2018-11-06
CHINA NUCLEAR POWER TECH RES INST CO LTD +3
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Problems solved by technology

Because lead-bismuth alloys are corrosive, and the oxygen concentration of liquid lead-bismuth has a great influence on the physical properties of lead-bismuth, this system is not suitable for lead-bismuth experiments.
[0005] However, there are still many shortcom...

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  • Experimental system for thermal-hydraulic characteristics and corrosive properties of liquid lead-bismuth alloy

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Embodiment Construction

[0048] In order to make the object, technical solution and advantages of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings.

[0049] Such as figure 1 As shown, in Embodiment 1 of the present invention, a liquid lead-bismuth alloy thermal hydraulic characteristics and corrosion characteristics experimental system is provided, including a liquid lead-bismuth circulation experimental device; wherein,

[0050] The liquid lead-bismuth circulation experimental device includes:

[0051] Liquid main pipeline L1;

[0052] The driving pump group 2, the first pressure transmitter 3, the first flow meter 4, the preheater 5, the second Pressure transmitter 6, first lead-bismuth valve LBE-1, glove box 7, oxygen control system 8, purification system 9, second flow meter 10, second lead-bismuth valve LBE-2, third pressure transmitter 11 , the third lead-bismuth valve LBE-3, heat exchanger 12, the fou...

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Abstract

The invention provides an experimental system for thermal-hydraulic characteristics and corrosive properties of a liquid lead-bismuth alloy. The experimental system comprises a liquid lead-bismuth cycling experiment device, wherein the liquid lead-bismuth cycling experiment device specifically comprises a power pump group, a preheater, a first experimental section, a second experimental section, aheat exchanger, an oxygen control system, a purification system, an expansion box, a storage box, a plurality of flow meters, a plurality of pressure transmitters and a plurality of lead-bismuth valves. By controlling opening or closing of different lead-bismuth valves, different loops are selected for completing experiments on the thermal-hydraulic characteristics and corrosive properties of equipment associated with the liquid lead-bismuth alloy in different experimental sections of the system, as well as experiments on compatibility characteristics of equipment materials and lead-bismuth.With implementation of the system, defects in the prior art can be overcome, and analytical study on the thermal-hydraulic characteristics and corrosive properties of the liquid lead-bismuth alloy isrealized.

Description

technical field [0001] The invention relates to the technical field of nuclear energy, in particular to an experimental system for thermal hydraulic characteristics and corrosion characteristics of a liquid lead-bismuth alloy. Background technique [0002] Nuclear energy has occupied an increasingly important position in the energy field of the world today. With the development of nuclear energy, how to make full use of limited uranium resources and effectively deal with nuclear waste has increasingly attracted people's attention. Liquid lead-bismuth alloy cooling reactor is an effective way to solve the above problems. As a coolant, liquid lead-bismuth alloy has good thermal conductivity, but due to its active chemical properties, high melting point and corrosiveness, it is extremely difficult to study thermal hydraulic performance and corrosion performance. [0003] For the design and construction of fast reactors and the safety analysis of fast reactor operation, the res...

Claims

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Application Information

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IPC IPC(8): G01N33/20G01N25/20G01N17/00
CPCG01N17/006G01N25/20
Inventor 梁峻铭梁振辉刘欣周炜翔张会勇吴小航
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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