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CHF relational expression DNBR limit value statistical determination method based on correction method

A technique for determining methods and relational expressions, applied in the field of thermal hydraulic design and safety analysis of nuclear reactors

Active Publication Date: 2019-12-31
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

[0005] The purpose of the present invention is to provide a method for statistically determining the DNBR limit value of the CHF relational formula based on the correction method, so as to solve the problem of strict, accurate and relatively conservative acquisition of the DNBR limit value in the CHF relational formula

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  • CHF relational expression DNBR limit value statistical determination method based on correction method
  • CHF relational expression DNBR limit value statistical determination method based on correction method
  • CHF relational expression DNBR limit value statistical determination method based on correction method

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Embodiment Construction

[0066] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0067] like figure 1 Shown, a kind of CHF relational formula DNBR limit statistical determination method based on correction method, this method specifically comprises the following steps:

[0068] Step 1, collecting and obtaining the CHF experimental data of the fuel assembly;

[0069] Step 2. Obtain the M / P data of the position of the experimental burn point on the basis of the determined fuel assembly CHF relational expression;

[0070] Step 3, carry out Bartlett test to the M / P data of experiment burn point position;

[0071] Utilize the Bartlett test to check the homogeneity of variance of the M / P data (M / P: the CHF value predicted by the experimentally measured CHF value / CHF relational formula) of the burn point position of the collected fuel assembly;

[0072]

[0073]

[0074]

[0075] Among them, ν t is the sampl...

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Abstract

The invention relates to the technical field of nuclear reactor thermal hydraulic design and safety analysis, and particularly discloses a CHF relational expression DNBR limit value statistical determination method based on a correction method. The CHF relational expression DNBR limit value statistical determination method specifically comprises the following steps: 1, acquiring CHF experimental data of a fuel assembly; 2, obtaining M / P data of an experiment burning point position; 3, carrying out Bartlett inspection on M / P data at the position of the experimental burning point; 4, carrying out homogeneity test of a data mean value; 5, carrying out normal distribution inspection; 6, determining a DNBR limit value by using an Owen criterion; 7, when the M / P data cannot pass any one of the steps 3 to 5, correcting the degree of freedom by utilizing Sterhware; and 8, substituting the correction degree of freedom obtained in the step 7 into an Owen coefficient expression to solve and obtain an Owen coefficient so as to determine a DNBR limit value. According to the CHF relational expression DNBR limit value statistical determination method, a rigorous, accurate and relatively conservative CHF relational expression DNBR limit value can be obtained, and key parameters can be calculated for CHF relational expression development and CHF experimental data evaluation, and the most concerned design limit value is provided for a nuclear safety department.

Description

technical field [0001] The invention belongs to the technical field of thermal-hydraulic design and safety analysis of nuclear reactors, and in particular relates to a method for statistically determining the DNBR limit value of a CHF relational formula based on a correction method. Background technique [0002] The critical heat flux (Critical Heat Flux, CHF) relational expression is used to predict the critical heat flux value of the core, and the safety and economy of the core are closely related to the CHF relational expression. DNBR (Deviation from Nucleate Boiling Ratio) is defined as the ratio of the heat flux value calculated by the CHF relation to the local actual heat flux value. Accurately predicting the DNBR value of the reactor core is the core content of thermal-hydraulic design and safety analysis of the reactor, and is an important criterion for the safety of the reactor core in the steady-state thermal-hydraulic analysis and accident analysis of Type I, II a...

Claims

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Application Information

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IPC IPC(8): G06F17/18G21D3/00G21D3/06
CPCG06F17/18G21D3/005G21D3/06Y02E30/00
Inventor 刘伟杜思佳张渝张虹黄慧剑徐良剑刘余陆祺冷贵君李庆
Owner NUCLEAR POWER INSTITUTE OF CHINA
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