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Overall performance test platform for passive reactor core cooling system of large advanced pressurized water reactor nuclear power plant

A technology for core cooling and nuclear power plants, which is applied in the testing of mechanical components, testing of machine/structural components, measuring devices, etc., and can solve the requirements of complexity, system heat loss, large distortion of metal heat storage, and complex comprehensive proportional analysis Gap and other issues to achieve the effect of increasing diversity and improving accuracy

Pending Publication Date: 2019-05-17
STATE NUCLEAR HUAQING BEIJING NUCLEAR POWER TECH R & D CENT
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  • Abstract
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  • Claims
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AI Technical Summary

Problems solved by technology

There are large distortions in the friction loss, system heat loss, and metal heat storage in the full pressure, thin and tall benches, and there is no theoretical analysis guidance for the simulation of local thermal-hydraulic phenomena.
One of the main reasons is that for passive systems, some local thermal-hydraulic phenomena are more important and more complex. The original power volume is an overall and macro design method, which cannot be used for detailed local phenomena. good deal
This method still has some gaps in the requirements of complex and comprehensive proportional analysis of large-scale integral passive test systems

Method used

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  • Overall performance test platform for passive reactor core cooling system of large advanced pressurized water reactor nuclear power plant
  • Overall performance test platform for passive reactor core cooling system of large advanced pressurized water reactor nuclear power plant
  • Overall performance test platform for passive reactor core cooling system of large advanced pressurized water reactor nuclear power plant

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Embodiment Construction

[0024] The drawings and the following description describe alternative embodiments of the invention to teach those of ordinary skill in the art how to make and reproduce the invention. In order to teach the technical solutions of the present invention, some conventional aspects have been simplified or omitted. Those skilled in the art should understand that modifications or substitutions from these embodiments will fall within the protection scope of the present invention. Those of ordinary skill in the art will appreciate that the features described below can be combined in various ways to form multiple variations of the invention. As such, the invention is not limited to the alternative embodiments described below, but only by the claims and their equivalents.

[0025] now refer to figure 1 , The ACME test bench is based on the CAP1400 nuclear power plant as a prototype, adopts advanced proportional analysis method, and is designed according to the 1 / 3 height ratio and 10M...

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Abstract

The invention relates to an overall performance test platform for a passive reactor core cooling system of a large advanced pressurized water reactor nuclear power plant. An ACME test rack comprises aloop system and equipment completely simulating a prototype nuclear power plant, a system and equipment completely simulating a prototype nuclear power plant passive reactor core cooling system, a system and equipment partly simulating a reactor secondary circuit and a system and equipment partly simulating a reactor loop and connected with the reactor loop, wherein the loop system and equipmentcompletely simulates loop layouts of a four-in pipe and a two-out pipe of the prototype nuclear power plant, and the system and equipment completely simulating the prototype nuclear power plant passive reactor core cooling system proportionally simulates layouts and pipeline routs of the system and equipment.

Description

technical field [0001] The invention relates to the field of nuclear power tests, in particular to an overall performance test platform for a large-scale advanced pressurized water reactor passive core cooling system. Background technique [0002] The CAP1400 nuclear power plant is a third-generation large-scale advanced pressurized water reactor nuclear power plant independently developed by my country. It adopts a passive safety system to deal with nuclear power plant accidents and ensure the safety of the reactor. The "passive" design concept is a major innovation in the design of the safety system of the PWR nuclear power plant. It makes full use of the natural characteristics of the material, such as gravity, natural circulation, compressed gas expansion and other natural forces, and does not require pumps, AC power, 1E level The emergency diesel engine, as well as the corresponding support systems such as ventilation and cooling water, greatly simplifies the safety sys...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01M99/00G01M13/00
Inventor 李玉全常华健叶子申田芳陈炼王含房芳芳张陶石洋钟佳郝博涛杨福明崔明涛李代力王楠王嘉鹏
Owner STATE NUCLEAR HUAQING BEIJING NUCLEAR POWER TECH R & D CENT
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