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Experimental model for sodium-cooled pool type fast reactor natural circulation experiment

A technology of natural circulation and experimental model, applied in the field of reactor simulation experiments, can solve the problems of inability to complete the primary loop natural circulation capability verification experiment and the inability to simulate interactions, etc., to reduce the cost of experiments, the difficulty of equipment development, and the difficulty of processing technology , Reduce the effect of difficult processing technology

Active Publication Date: 2021-04-20
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The only few documents and materials cannot simulate the interaction between components in the actual reactor, and cannot complete the content of the natural circulation capability verification experiment of the primary loop

Method used

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  • Experimental model for sodium-cooled pool type fast reactor natural circulation experiment
  • Experimental model for sodium-cooled pool type fast reactor natural circulation experiment
  • Experimental model for sodium-cooled pool type fast reactor natural circulation experiment

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Embodiment Construction

[0039] The present invention will be further described below in conjunction with the accompanying drawings and embodiments.

[0040] Such as Figure 1 to Figure 7 As shown, the present invention provides an experimental model for natural circulation experiments of sodium-cooled pool type fast reactors, including an upper head 1, an upper cylinder 3, a lower cylinder 4 and a lower head connected in sequence from top to bottom 2 Cylindrical shell 5 formed by sealing (these components constitute the outer boundary shell of the entire experimental model, and play an important role in enveloping experimental components and working fluid, the main external dimensions of the model: diameter: 3500mm, height about 3600mm), The upper head 1 and the upper cylinder 3 form a hot pool, the lower cylinder 4 and the lower head 2 form a cold pool, the simulated core 13 located in the center of the shell 5, and the central measurement column simulation piece 17 located above the simulated core ...

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Abstract

The invention belongs to the technical field of reactor simulation experiments, and particularly relates to an experimental model for a sodium-cooled pool type fast reactor natural circulation experiment. The experimental model comprises a cylindrical shell formed by sequentially connecting an upper sealing head, an upper cylinder body, a lower cylinder body and a lower sealing head from top to bottom in a sealed mode, the upper sealing head and the upper cylinder body form a hot pool, and the lower cylinder body and the lower sealing head form a cold pool. The experimental model also comprises a simulated reactor core located in the center of the shell, a central measuring column simulation part located above the simulated reactor core, a large grid plate header simulation part located below the simulated reactor core, a DR type heat exchanger simulation part arranged in the hot pool, a DL type heat exchanger simulation part arranged in the cold pool, and an M-type heat exchanger simulation part arranged between the hot pool and the cold pool in a penetrating manner. Working media in the cold pool can be powered by an external circulating pump to sequentially enter the large grid plate header simulation part and the simulation reactor core to enter the hot pool, and then return to the cold pool again after exchanging heat with the M-type heat exchanger simulation part.

Description

technical field [0001] The invention belongs to the technical field of reactor simulation experiments, and in particular relates to an experimental model used for natural circulation experiments of sodium-cooled pool type fast reactors. Background technique [0002] After an accident in a sodium-cooled pool fast reactor, whether the primary loop system coolant can establish natural circulation and whether the natural circulation capability can take away the decay heat generated by the core is one of the key issues to be considered in reactor design. The thermal-hydraulic phenomenon of the accident waste heat removal system is complicated. At the same time, it is necessary to explore the operating characteristics of the passive waste heat removal system under the conditions of a sodium-cooled pool fast reactor power failure and a steam generator loss of feedwater accident, evaluate the design and analysis program model, and verify the passive waste heat of the sodium-cooled p...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 程道喜陈东张学锋杜开文齐晓光翟伟明周平周志伟
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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