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A method of preventing meltdown in a reactor from damaging a pressure vessel and a system for implementing the method

A technology for reactor vessels and pressure vessels, applied in reactors, greenhouse gas reduction, nuclear engineering, etc., can solve problems such as insignificant cooling effect, large volume of cooling water tank, and no flow control of cooling water injection, so as to avoid adverse interactions, The effect of simple and reasonable design and high reliability

Inactive Publication Date: 2017-08-04
STATE NUCLEAR POWER TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the method proposed in this patent still has certain limitations
IRVR is injected through the main cooling pipe. This method has certain risks. If the main cooling pipe is damaged, the IRVR injection will fail.
There is no flow control for cooling water injection, so if the injection is too slow, the cooling effect will not be obvious, and if the injection is too fast, it may cause a large amount of hydrogen and water vapor to be generated in a short time
In addition, this method does not determine the amount of water injected. On the one hand, if the amount of water injected is too small, it cannot fully satisfy the residual heat taken out of the core and obtain the desired technical effect. On the other hand, if the amount of water injected is too large, the volume of the cooling water tank will be too large. , or it is necessary to replenish cooling water from outside the reactor, so that the cooling water tank occupies too much space in the containment vessel, or it is necessary to replenish cooling water to specially designed pipelines, which makes the design of the reactor interior tend to be complicated

Method used

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  • A method of preventing meltdown in a reactor from damaging a pressure vessel and a system for implementing the method
  • A method of preventing meltdown in a reactor from damaging a pressure vessel and a system for implementing the method
  • A method of preventing meltdown in a reactor from damaging a pressure vessel and a system for implementing the method

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Experimental program
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Effect test

Embodiment

[0066] like figure 1 As shown, when the nuclear power reactor (with a power of 1400MWe) loses cooling, the ERVC system is immediately started to cool the reactor pressure vessel, and at the same time monitor the core outlet temperature, that is, the outlet temperature at the cooling pipe 420 . If the core outlet temperature monitoring device detects that the core outlet temperature continues to rise to 650°C, the automatic control system (not shown) starts the injection IRVR system in the reactor vessel, opens the valve 21 on the pipeline 210, and will be installed in the IRVR injection box 28m out of 20 3 The boron-containing aqueous solution is injected into the reactor pressure vessel through the pipeline 210 and the direct injection pipeline 510, and the injection time is about 10 minutes, during which the ERVC system keeps working.

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Abstract

The invention relates to a method used for preventing pressure vessels from melting damages caused by molten materials in reactors. The method comprises following steps: when nuclear reactor accidents happen, a reactor container in-vessel injection IRVR system is activated, and cooling water with a volume no less than V(m<3>) is injected into the pressure vessels, wherein V=0.02*P0, P0 represents reactor core power, and the unit of P0 is MWe. The invention also relates to the reactor container in-vessel injection IRVR system which is used for the method.

Description

technical field [0001] The invention relates to the technical field of nuclear safety, more particularly to the technical field of preventing reactor core molten material from melting and damaging reactor pressure vessels when a major accident occurs in a nuclear power plant. Background technique [0002] In the design of nuclear power plants, nuclear safety is the primary issue to be considered. After the Three Mile Island nuclear power plant accident in the United States in 1979 and the Chernobyl nuclear power plant accident in the former Soviet Union in 1986, the prevention and mitigation of severe accidents have become factors that must be considered in the design of nuclear power plants. After the Fukushima accident in Japan in 2011, the prevention and mitigation of severe nuclear power plant accidents have attracted more attention from the public, governments and safety regulatory authorities of various countries. The risks of nuclear power plants mainly come from pot...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C15/18
CPCY02E30/30
Inventor 赵瑞昌刘志弢
Owner STATE NUCLEAR POWER TECH
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