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Method for determining design pressure limit value of containment annulus of nuclear power plant

A nuclear power plant containment and annular space technology, which is applied in design optimization/simulation, calculation, electrical digital data processing, etc., can solve the inaccurate pressure value at the slit of the outer wall of the containment vessel, and the inability to meet the pressure limit design of the containment annular space To very safe, reliable and other issues, to achieve the effect of design safety

Active Publication Date: 2017-08-25
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

[0004] The purpose of the present invention is to provide a method for determining the design pressure limit of the containment annular space of a nuclear power plant in response to the requirements of nuclear power plant safety design, so as to solve the inaccurate pressure value at the slit of the outer wall of the containment determined by the existing empirical formula, resulting in The design of the pressure limit of the annular space cannot reach a very safe and reliable technical problem

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  • Method for determining design pressure limit value of containment annulus of nuclear power plant
  • Method for determining design pressure limit value of containment annulus of nuclear power plant

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[0019] The specific implementation manners of the present invention will be further described below in conjunction with the accompanying drawings.

[0020] The process flow of the exemplary method for determining the design pressure limit of the containment annular space of a nuclear power plant according to the present invention is as follows: figure 1 Shown (wherein the simplified principle of the radioactive material transport model is as follows figure 2 shown), including the following steps.

[0021] (1) The formula for calculating the design pressure limit of the containment annular space is p in =p out -Δp, where p in Limits for the design pressure of the containment annular space, p out is the average pressure at the gap of the containment outer wall, Δp is the pressure difference between the containment outer wall and the annular space;

[0022] (2) Calculation method of the average pressure at the gap of the containment outer wall:

[0023] a. The k-ε turbulen...

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Abstract

The invention belongs to the technical field of nuclear power plant safety design and relates to a method for determining a design pressure limit value of a containment annulus of a nuclear power plant. The method sequentially comprises the steps of determining a pressure value of a gap of a containment outer wall; and determining a pressure difference of the containment annulus and the containment outer wall, wherein a CFD computing model is adopted in the step of determining the pressure value of the gap of the containment outer wall. By utilizing the method for determining the design pressure limit value of the containment annulus of the nuclear power plant, the pressure value of the gap of the containment outer wall can be determined more accurately in comparison with estimation by a conventional empirical formula; and through a built radioactive material transportation model, the flow characteristics of the gap of the outer-layer containment can be analyzed. Through the two improvements, the pressure difference of the containment annulus and the containment outer wall can be obtained more accurately, so that the design of the pressure limit value of the containment annulus is safer and more reliable.

Description

technical field [0001] The invention belongs to the technical field of safety design of nuclear power plants, and relates to a method for determining the design pressure limit of the annular space of the containment shell of the nuclear power plant. Background technique [0002] At present, the domestic third-generation nuclear power safety technology adopts a double-layer containment design. Penetrations, isolation devices, personnel gates, equipment gates, etc. that are installed and pre-embedded in the containment wall are affected by materials, construction and other factors. After the installation is completed, there will be certain gaps. In order to prevent radioactive substances from leaking through the gaps in the containment, a ventilation system needs to be installed in the annular space of the two layers of containment to ensure that the direction of the airflow penetrating through the potential gaps of the outer containment is from outside to inside. Therefore, ...

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Application Information

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IPC IPC(8): G06F17/50
CPCG06F30/20Y02E30/30
Inventor 温华郭静涛苑晓东刘鹏飞戴一辉孙立臣
Owner CHINA NUCLEAR POWER ENG CO LTD
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