Method for acquiring fine distribution of reactor core three dimensional neutron flux density of reactor

Abstract

A method for acquiring fine distribution of the reactor core three dimensional neutron flux density of a reactor comprises the following steps: 1, carrying out geometric modeling to a reactor core, dividing computational domain, dispersing angle space, generating characteristic line, appointing materials for all computing regions, obtaining macroscopic section parameters and setting initial values for neutron flux density flux of a computed region, terminal condition of reactor and characteristic value; 2, calculating coefficient matrix required by the matrix method of each sub region and a part which is positioned at the right end and cannot be changed with the iterative computation; 3, seeking the density of thicknet neutron flux and correcting the density of one-dimensional and two dimensional thinnet neutron flux; 4, seeking the density of one-dimensional neutron flux of each lattice cell; 5, iterative solution of the density of the two dimensional thinnet neutron flux of each layer; and 6, updating three dimensional thicknet parameters, judging whether a characteristic value and the density of a three dimensional neutron flux are in convergence or not, if in convergence, turning to the step 3 for continuous iteration under convergence is achieved, namely, fine distribution of three dimensional neutron flux density can be obtained; and the fine distribution of the reactor core three dimensional neutron flux density of a reactor can be obtained quickly.

Description

technical field [0001] The invention relates to the fields of nuclear reactor core design and reactor physical calculation, in particular to a method for obtaining fine distribution of three-dimensional neutron flux density in the reactor core. Background technique [0002] In order to ensure the safety of reactor core design and operation, it is necessary to accurately and quickly calculate the three-dimensional neutron flux density distribution in the reactor and related equipment. [0003] The "two-step method", the traditional reactor physical analysis and calculation method widely used at present, is based on the equivalent homogenization theory. As the reactor core design becomes more and more complex and the safety requirements are getting higher and higher, the "two-step method" cannot meet the requirements of engineering calculation gradually. [0004] The so-called "two-step method", the first step is to perform multi-group neutron transport calculations on variou...

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Problems solved by technology

However, as far as the current calculation conditions are concerned, it is not realistic to directly solve the three-dimensional neutron transport equation for the core of a large nuclear reactor.

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