A method to prevent nuclear power plant bypass type loca

A bypass type, nuclear power plant technology, used in nuclear power generation, nuclear engineering, reactors, etc., can solve problems such as leakage, achieve the effect of improving safety, easy implementation, and small design changes

Active Publication Date: 2015-08-19
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

If the cooling coil or its connecting parts break, the primary circuit fluid will leak into the equipment cooling water system. If the related equipment cooling water pipes rupture, the primary circuit fluid will leak through the equipment cooling water pipes, causing nuclear power plant Bypass LOCA

Method used

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  • A method to prevent nuclear power plant bypass type loca
  • A method to prevent nuclear power plant bypass type loca
  • A method to prevent nuclear power plant bypass type loca

Examples

Experimental program
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Embodiment

[0022] The following takes the main pump heat shield and equipment cooling water system piping as examples to illustrate the scheme design.

[0023] Such as Figure 4 As shown, the equipment cooling water system pipe 42 provides cooling water to the main pump heat shield 41 . If the heat shield 41 of the main pump breaks, the fluid of the primary circuit leaks into the equipment cooling water pipeline 42 , and if the equipment cooling water pipeline outside the containment communicating with it breaks, the fluid of the primary circuit leaks out of the containment. In order to prevent the occurrence of bypass type LOCA outside the containment, the present invention is applied to install a double redundant isolation device on the equipment cooling water pipeline 42 inside the containment to ensure the effective isolation of the equipment cooling water pipeline 42 and prevent primary circuit Fluid leaked out of containment.

[0024] On the equipment cooling water pipeline 42, t...

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PUM

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Abstract

The invention relates to nuclear power plant design technology, and particularly relates to a method for preventing by-pass type LOCA (Loss of Coolant Accident) of a nuclear power plant. The invention relates to nuclear power plant design technology, and particularly relates to a method for preventing by-pass type LOCA of a nuclear power plant. According to the method, a redundant isolation device is arranged on a primary coolant circuit pipeline, and / or an other non-primary coolant circuit system pipeline communicating with primary coolant circuit fluid, and / or a system pipeline, which the primary coolant circuit fluid may leak into. When the non-primary coolant circuit pipeline ruptures, the redundancy isolation device ensures the isolation of the non-primary coolant circuit pipeline, so as to prevent leakage of the primary coolant circuit fluid through the non-primary coolant circuit pipeline. The method provided by the invention has little change on the original design of the nuclear power plant system but obvious actual effect, is convenient for implement, and improves safety of the nuclear power plant.

Description

technical field [0001] The invention relates to nuclear power plant design technology, in particular to a method for preventing nuclear power plant bypass type LOCA. Background technique [0002] A loss of coolant accident refers to an accident in which a breach or rupture occurs in the pressure boundary of the main circuit of the reactor, and a part or most of the coolant leaks out. [0003] According to the size of the breach, dehydration accidents can usually be divided into large breaches, medium and small breaches. In the small breach loss of water accident, the depressurization rate of the primary circuit is slow, and the core may be exposed for a long time in the high pressure stage during the accident process, which may cause the fuel element to heat up and be damaged. Therefore, it is also necessary to prevent and alleviate the loss of water accidents in small breaches. [0004] Bypass LOCA of nuclear power plants: the coolant of the primary circuit enters other s...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C15/02
CPCY02E30/40Y02E30/30
Inventor 王志超丁亮李军
Owner CHINA NUCLEAR POWER ENG CO LTD
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