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Method for improving external critical heat flux density of pressure vessel

A critical heat flux density, pressure vessel technology, applied in reactors, greenhouse gas reduction, nuclear engineering, etc., can solve problems such as difficulty in making major design improvements

Pending Publication Date: 2021-03-19
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] The heat flux on the wall of the pressure vessel is acted on the wall by the molten material after the core melts. Its magnitude is related to factors such as the power of the core and the total water content of the core. It is generally difficult to relate to the core system of the normal operation of the reactor Make major design improvements

Method used

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  • Method for improving external critical heat flux density of pressure vessel
  • Method for improving external critical heat flux density of pressure vessel
  • Method for improving external critical heat flux density of pressure vessel

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Embodiment

[0021] In the event of a severe accident in a nuclear power plant, if the exit temperature of the core exceeds a certain limit, the operator will be required to initiate the IVR strategy. The IVR strategy injects (by gravity or pumps) an external source of water into the reactor cavity. Among them, the water close to the wall of the pressure vessel will heat up to a boiling state, forming water vapor and leaving the reactor cavity. However, with the subsequent replenishment of water sources, such as water vapor condensed backflow, or the replenishment of small flow pumps, it can be stored in the reactor cavity compartment. Maintain a certain amount of water to form a natural cycle.

[0022] like Figure 1 to Figure 4 Shown, the method for improving the external critical heat flux of pressure vessel under the serious accident of nuclear power plant of the present invention, it comprises the steps:

[0023] (1) A number of mixing rotors 4 are installed in the reactor cavity co...

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Abstract

The invention aims to disclose a method for improving the external critical heat flux density of a pressure vessel. Compared with the prior art, the fluid between the outer wall surface of a reactor pressure vessel and a heat preservation layer can be stirred and mixed without depending on external alternating current, so that cold fluid on the side of the heat preservation layer cools the outer wall surface of the pressure vessel, and the steam content on the side of the wall surface is reduced, the CHF value outside the reactor pressure vessel can be greatly improved at the early stage of anaccident; even under the condition that a storage battery is exhausted, the fluid between the heat preservation layer and the wall surface of the pressure vessel can be stirred and mixed by means ofnatural circulation of the fluid in the reactor cavity, the CHF value of the outer wall surface of the pressure vessel is slightly increased, and the purpose of the invention is achieved.

Description

technical field [0001] The invention relates to a method for increasing the external critical heat flux density of a pressure vessel, in particular to a method for increasing the external critical heat flux density of a pressure vessel under a severe accident in a nuclear power plant. Background technique [0002] In-reactor retention of melt (IVR) is currently one of the most promising and important mitigation strategies for severe reactor accidents. The IVR measure is to inject water into the reactor cavity under the condition of an accident in the nuclear power plant, so that the reactor pressure vessel is immersed in water, relying on the boiling of water to cool the pressure vessel wall and maintain the integrity of the pressure vessel. However, the success of IVR measures needs to meet certain conditions, such as the heat flux on the pressure vessel wall must be less than the local critical heat flux (CHF). The ratio of the heat flux on the wall of the pressure vessel...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/18G21C15/12G21C15/243
CPCG21C15/185G21C15/12G21C15/243Y02E30/30
Inventor 顾培文史国宝曹克美张琨
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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