Primary circuit coolant charging and discharging system for nuclear power plant reactor

A technology for a coolant and a reactor, applied in the field of nuclear power, can solve the problems of difficulty in discharging and exhausting lead-based coolant, difficulty in overhauling and replacing equipment in the main vessel, and difficulty in repairing weld seams in the main vessel, etc. Risk of exposed core, easy maintenance, high safety effect

Inactive Publication Date: 2018-09-07
CHINA NUCLEAR POWER TECH RES INST CO LTD +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

In this case, it is difficult to discharge and exhaust the lead-based coolant by simply using a pump to directly pump the coolant in the main container
If the primary circuit coolant discharge measures are not provided, it will be difficult to repair and replace the equipment in the main container, and it will be difficult to repair the welds in the main container

Method used

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  • Primary circuit coolant charging and discharging system for nuclear power plant reactor

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Embodiment Construction

[0020] In the following description, specific details such as specific system structures and technologies are presented for illustration rather than limitation, so as to thoroughly understand the embodiments of the present invention. It will be apparent, however, to one skilled in the art that the present invention may be practiced in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.

[0021] In order to illustrate the technical solutions described in the present invention, the following description will be made through specific embodiments in conjunction with the accompanying drawings.

[0022] figure 1 Shown is that the embodiment of the present invention provides a nuclear power plant reactor primary circuit coolant charging and discharging system, which can be applied to the cooli...

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Abstract

The invention discloses a primary circuit coolant charging and discharging system for a nuclear power plant reactor. The primary circuit coolant charging and discharging system comprises a primary circuit pressurization subsystem used for charging high-temperature gas into a primary circuit reactor main vessel for pressurization when a coolant is discharged into a primary circuit, and a coolant delivery subsystem which comprises a primary circuit coolant charging circuit, a primary circuit coolant discharging circuit, a coolant delivery pump and a coolant storage device, wherein the coolant storage device is connected with the primary circuit reactor main vessel through the primary circuit coolant charging circuit and the primary circuit coolant discharging circuit; the coolant delivery pump is arranged in the primary circuit coolant discharging circuit; the primary circuit coolant charging circuit is used for charging a coolant into the primary circuit reactor main vessel; and the primary circuit coolant discharging circuit is used for pumping the coolant in the primary circuit reactor main vessel to the coolant storage device. According to the invention, through cooperation of primary circuit gas phase pressurization with discharging of a primary circuit high-density coolant pumped by the coolant delivery pump, the coolant is pressurized to be discharged, so devices in the main vessel can be easily maintained and replaced.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a nuclear power plant reactor primary circuit coolant charging and discharging system. Background technique [0002] For nuclear reactors that use heavy metals or heavy metal alloys as coolants, the coolant density is relatively high. Under the same pressure difference, the liquid column height of the liquid alloy can only reach 1 / 10 of the water column height; while the reactor main container is large, the normal coolant liquid The level is usually higher than 5 meters; at the same time, the position of the coolant flushing pipe and the upper opening of the main container should be avoided to be lower than the normal liquid level, so as to avoid the risk of core exposure due to the loss of primary circuit coolant caused by pipe rupture. In this case, it is difficult to discharge and exhaust the lead-based coolant by simply using a pump to directly suck the coolant in the m...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21D1/04
CPCG21D1/04Y02E30/00
Inventor 赵达魏川清陈丰彭浩张立德张守杰
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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