A method for obtaining continuous spatial distribution of neutron flux density in fuel rods

Abstract

The invention discloses a method for obtaining continuous space distribution of neutron-flux density in fuel rods. The method comprises the following steps of: designing a function expansion coefficient by adoption of a Monte Carlo simulation method; and reconstructing continuous flux distribution on the space by utilizing the obtained expansion coefficient so as to solve the problem that the Monte Carlo method for calculating flux distribution in fuel rods is not exquisite. Compared with the traditional Monte Carlo method, the method has the advantages that a statistical calculation functionof continuous flux distribution is added, superfine counting grids do not need to be divided on the same accuracy class so that an expectant variance level can be achieved without using an oversize simulation history number, and the particle simulation and counting process of the method are based on the traditional Monte Carlo method so that the counting response amount does not use traditional integral amount and carries out statistical analysis on the expansion coefficient, so that relatively high universality and replaceability are provided, and development can be conveniently carried out on the basis of existing calculation programs.

Description

technical field [0001] The invention relates to the field of nuclear reactor core design calculation, in particular to a method for obtaining continuous spatial distribution of neutron flux density in fuel rods. Background technique [0002] In the process of nuclear reactor core design, in order to carefully investigate the nuclide consumption process and surplus status in the fuel rods, it is necessary to carry out detailed numerical simulation calculations of neutron transport in the whole life cycle. Among many methods, the Monte Carlo method can combine the physical process of the interaction between the particle and the nucleus of the medium to obtain the distribution of the neutron flux density after the particle is transported in a specific medium. Since the modeling process of this method does not introduce approximation, based on statistical theory, this method converges to the true solution when the number of samples is large enough, so this method has high calcul...

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Problems solved by technology

[0006] In order to overcome the problems existing in the above-mentioned prior art, the object of the present invention is to provide a method for obtaining the continuous spatial distribution of the neutron flux density in the fuel rod, using the Monte Carlo simulation method, counting the expansion coefficient of the function, and then using the statistically obtained The expansion coefficient reconstructs the continuous flux distribution in space, and solves the problem of inaccurate calculation of the flux distribution by the traditional Monte Carlo method; compared with the traditional Monte Carlo method, the method of the present invention increases the statistical calculation function of the continuous flux distribution; At the same level of accuracy, there is no need to divide too fine a counting grid, so that the expected variance level can be achieved without a large simulation history; the particle simulation and counting process of this method is based on the traditional Monte Carlo method, and the counting response is no longer Using traditional integral quantities, but statistical expansion coefficients, has high versatility and replaceability, and is convenient to develop on the basis of existing calculation programs

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