Simulation apparatus and simulation method for heat flux density of lower head of pressure vessel

A technology of pressure vessel and heat flux, applied in nuclear reactor monitoring, reactor, nuclear power generation, etc.

Active Publication Date: 2013-10-16
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] The purpose of the present invention is to provide a simulation device and simulation method applied to the heat flux density of the low

Method used

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  • Simulation apparatus and simulation method for heat flux density of lower head of pressure vessel
  • Simulation apparatus and simulation method for heat flux density of lower head of pressure vessel
  • Simulation apparatus and simulation method for heat flux density of lower head of pressure vessel

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Embodiment

[0035] Such as figure 1 As shown, the present invention is a simulation device for the heat flux density of the lower head of a pressure vessel. The main body is an arc simulator 1. The arc simulator 1 is formed by bending a cuboid, and heating elements are distributed inside it, which can simulate different Kind of heat flux distribution, such as figure 2 As shown, in the direction of top view, the arc-shaped simulator 1 is rectangular, while the slice structure 2 of the hemispherical lower head is fan-shaped, that is, the slice structure 2 of the hemispherical lower head is the image 3 The shown hemispherical lower head structure 3 is cut according to a certain angle, and the projection of the cut out structure is fan-shaped. When using it, follow the steps below:

[0036] (a) According to the design results of the nuclear reactor, the outer radius R of the lower head of the nuclear reactor pressure vessel is obtained 下封头 , cooling flow and the heat flux distribution o...

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Abstract

The invention discloses a simulation apparatus and a simulation method for heat flux density of the lower head of a pressure vessel. The simulation apparatus comprises an arc simulator which is a cuboid as a whole; the arc simulator bends towards one of the side surfaces of the arc simulator to form a quarter circular ring with a rectangular cross section, the external diameter of the arc simulator is R, the internal diameter of the arc simulator is R-B, B is the thickness of the arc simulator, and the width of the arc simulator is Am. The simulation apparatus provided by the invention can simulate heat power of core melts under different accident conditions and cooling flow of the lower head at the same time; the apparatus can also simulate heating of the core melts under severe accident conditions; the apparatus cooperates with other structures to form a cooling channel together; and the apparatus is applicable to experiments on flow and heat transfer characteristics and critical heat flux density of the external surface of the lower head of the pressure vessel under severe accident conditions in a laboratory, can acquire the limit value of the critical heat flux density of the external surface of the lower head and provides a basis for designing and validity evaluation of a severe accident mitigation system.

Description

technical field [0001] The invention relates to the field of simulation equipment required for the study of severe accidents of nuclear reactors, in particular to a simulation device and a simulation method for the heat flux density of the lower head of a pressure vessel. Background technique [0002] Since humans began to use nuclear energy, there have been many serious nuclear leakage accidents around the world, such as the Three Mile Island nuclear leakage accident in the United States, the Chernobyl nuclear leakage accident in the former Soviet Union, and the Fukushima nuclear leakage accident in Japan. Through the analysis of the development and treatment process of the above-mentioned nuclear leakage accident, it can be found that keeping the core melt in the pressure vessel and ensuring the integrity of the reactor pressure vessel can greatly alleviate the further development and deterioration of the severe accident. Now, there is a relatively complete reactor melt re...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 张震熊万玉王雄李朋洲卓文彬
Owner NUCLEAR POWER INSTITUTE OF CHINA
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