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Method and device for quantifying acquisition uncertainty of pressurized water reactor nuclear design software package

A deterministic, pressurized water reactor technology, applied in the field of nuclear reactor core, can solve problems such as unreasonable assumptions

Active Publication Date: 2022-01-28
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] The technical problem to be solved by the present invention is that heat flux density heat pipe factor F in the prior art Q , nuclear enthalpy rise heat pipe factor F ΔH In the method of obtaining uncertainty of parameters such as Q , F ΔH Unreasonable assumptions exist in the quantification process of indirect measurement parameters uncertainty
Compared with the prior art, the present invention can realize direct measurement parameters and solve the problem of F Q , F ΔH Unreasonable assumptions in the uncertainty quantification process of indirect measurement parameters, etc., perfected the confirmation system of the PWR nuclear design software package

Method used

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  • Method and device for quantifying acquisition uncertainty of pressurized water reactor nuclear design software package
  • Method and device for quantifying acquisition uncertainty of pressurized water reactor nuclear design software package
  • Method and device for quantifying acquisition uncertainty of pressurized water reactor nuclear design software package

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Embodiment 1

[0056] like figure 1 as shown, figure 1 It is a flow chart of a method for quantifying the uncertainties of the PWR nuclear design software package of the present invention, that is, a logic flow chart of the PWR nuclear design software package calculation uncertainty quantification method;

[0057] The present invention is a method for quantifying the acquisition uncertainty of a pressurized water reactor nuclear design software package, the method comprising:

[0058] Obtain the measured data of critical devices and power plants, as well as the calculation data of the physical design program;

[0059] Based on the acquired data, analyze whether the data is a direct measurement parameter;

[0060] If it is a direct parameter parameter, then use the direct measurement parameter method to carry out statistics on the deviation between the calculated value and the measured value, and calculate the uncertainty of the direct measurement parameter; wherein, the direct measurement ...

Embodiment 2

[0082] Such as figure 2 As shown, the difference between this embodiment and Embodiment 1 is that this embodiment provides a device for quantifying the acquisition uncertainty of the PWR nuclear design software package, and the device supports the quantitative PWR described in Embodiment 1. The method for obtaining the uncertainty of the core design software package, the device includes:

[0083] The acquisition unit is used to obtain the measured data of the critical device and the power plant, and obtain the calculation data of the physical design program at the same time;

[0084] The data judging unit is used to analyze whether the data is a direct measurement parameter according to the acquired data;

[0085] The uncertainty calculation unit of the directly measured parameter is used to judge the data as a direct parameter according to the data judging unit, then use the direct measurement parameter method to perform statistics on the deviation between the calculated va...

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Abstract

The invention discloses a method and device for quantifying the acquisition uncertainty of a pressurized water reactor nuclear design software package, and the method comprises the steps: obtaining actual measurement data of a critical device and a power plant, and obtaining calculation data of a physical design program at the same time; analyzing whether the data is a direct measurement parameter according to the acquired data; if the parameter is a direct parameter, carrying out deviation statistics on a calculated value and a measured value by adopting a direct measurement parameter method, and calculating to obtain the uncertainty of the direct measurement parameter; and if the parameters are indirect measurement parameters, adopting an indirect measurement parameter decomposition method to decompose the data, abandoning original unreasonable hypotheses, and obtaining calculation uncertainty through a disturbance method. Compared with the prior art, the invention has the advantages that the problem of unreasonable assumption in the uncertainty quantification process of indirect measurement parameters such as FQ and F[delta]H is solved, and a pressurized water reactor nuclear design software package confirmation system is perfected.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor cores, in particular to a method and device for quantifying the acquisition uncertainty of a pressurized water reactor nuclear design software package. Background technique [0002] The software validation (Validation) process is a necessary process before the software is applied to the PWR refueling design calculation and safety analysis and evaluation. Determining the uncertainty and applicability of calculation procedures is the main purpose of software verification and validation. PWR nuclear design software mainly includes component program and core program. The verification of the component calculation program is mainly to ensure the correctness and scope of the parameters used in the core (few group homogenization constant and power reconstruction shape factor), mainly by measuring the reactivity parameters, neutron value, and burnup of the core. and rod power distribution and oth...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G21C17/00G06F119/08
CPCG06F30/20G21C17/00G06F2119/08Y02E30/30
Inventor 彭星杰吴屈张斌周冰燕赵文博卢宗健李庆
Owner NUCLEAR POWER INSTITUTE OF CHINA
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