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Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups

A technology of fuel consumption and cross-section, which is applied in the measurement of nuclear data and the safety and economic fields of nuclear reactors. It can solve the problems that the sensitivity coefficient cannot be calculated accurately and effectively, and achieve the effect of high-efficiency sensitivity coefficient

Active Publication Date: 2016-03-23
XI AN JIAOTONG UNIV
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Problems solved by technology

[0005] In order to accurately and effectively solve the sensitivity coefficient of the effective multiplication factor to the nuclear cross section under different burnups, the present invention proposes an efficient and high-precision calculation method based on the time-dependent first-order generalized perturbation theory and neutron transport theory - to obtain different The method of the sensitivity coefficient of the effective multiplication factor to the cross-section under the burnup makes up for the defect that the existing method cannot accurately and effectively calculate the sensitivity coefficient of the effective multiplication factor to the nuclear cross-section under different burnups

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  • Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups
  • Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups
  • Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups

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Embodiment Construction

[0114] The method of the present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0115] Such as figure 1 As shown, a method of obtaining the sensitivity coefficient of the effective multiplication factor to the cross-section under different burnups in the present invention comprises the following steps:

[0116] Step 1: Carry out forward burnup calculation, and calculate the effective self-screening cross-section, middle angular flux density, neutron conjugate angular flux density and nucleon density of each nuclide at each burnup point, as figure 2 As shown, the forward fuel consumption calculation specifically includes the following contents:

[0117] 1) Read the multi-group micro-section and burnup chain information of each nuclide. The multi-group micro-section adopts the 69-group energy group structure of WIMSD, and the burnup chain of each nuclide also adopts the burnup chain in the WIMSD burnup libr...

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Abstract

The present invention discloses a method for obtaining sensitivity coefficients of an effective multiplication factor to a section under different burnups. The method comprises: 1, performing forward burnup calculation: first, using a subgroup method to calculate an effective self-shielding section of each nuclide, second, using a modular characteristic line method to solve a neutron angle flux density and a neutron conjugate angle flux density, and third, using a chebyshev rational approximation method to calculate a nuclear density of each nuclide; 2, performing conjugate burnup calculation: first, using the chebyshev rational approximation method to calculate an initial conjugate nuclear density of each nuclide, and then calculating a conjugate power, second, using the modular characteristic line method to calculate a generalized neutron transport angle flux and a generalized conjugate neutron transport angle flux, and third, calculating a conjugate initial nuclear density of each nuclide of a next step; and 3, calculating sensitivity coefficients of the section of each nuclide to an effective multiplication factor under different burnups. The method provided by the present invention solves a defect of the existing method that sensitivity coefficients of an effective multiplication factor to a nuclear section under different burnups cannot be accurately and effectively calculated.

Description

technical field [0001] The invention relates to the measurement of nuclear data and the safety and economic fields of nuclear reactors, in particular to a method for obtaining the sensitivity coefficient of the effective multiplication factor to the section under different burnups. Background technique [0002] The most basic and critical issue in reactor design is core physical calculation, the accuracy of physical calculation determines the safety and economy of reactor design. The calculation of effective multiplication factors under different burnups is an important part of physical calculations, and there are two main reasons affecting its calculation accuracy: one is the calculation software; the other is the deviation of the nuclear cross section itself. In recent years, with the continuous development of computer technology and calculation methods, the deviation caused by the calculation method has become smaller and smaller, while the deviation caused by the deviati...

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Application Information

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IPC IPC(8): G06F19/00
CPCG16Z99/00
Inventor 曹良志杨超吴宏春
Owner XI AN JIAOTONG UNIV
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