Method for calculating single rod power of overall reactor core

Abstract

Discloses is a method for calculating single rod power of an overall reactor core. The method includes steps of 1), determining geometrical and material parameters of a target nuclear reactor according a reactor core structure thereof; establishing an SP3 equation set of step 0 or step 2 neutron angular flux torque density according to a multigroup neutron transport theory; 2), adopting structural grids to subdivide structural geometry zones with corresponding shapes, and unstructured grids to subdivide unstructured geometry zones; 3), establishing a segment SP3 method, subjecting the SP3 equation set in the step 2) to numerical discretion by adopting approximate processing modes which are mutually compatible under a structural grid and the unstructured grid, and acquiring neutron-flux density on all grids of the nuclear reactor core by utilizing iterative algorithm to solve discrete algebraic equation set; 4), adopting the neutron-flux density acquired in the step 3) to calculate the single rod power of the overall reactor core. By reducing approximation from grid subdivision, approximation from the numerical discretion and iterative calculation process and approximation from component homogenization and component power reconstitution, the high-precision single rod power of the overall reactor core can be calculated.

Description

technical field [0001] The invention relates to the field of nuclear reactor core physical design and safety, in particular to a method for calculating single-rod power of the entire reactor core. Background technique [0002] The power of a single rod in the nuclear reactor core determines the position of the "hot spot" of the core, and can give the position in the core that is most likely to cause safety problems due to the temperature being higher than the material load, which is directly related to the safety rules. It is the nuclear reactor core The main parameters for evaluating the performance of the core in the design. The traditional method is to obtain single-rod power through component power reconstruction calculation after core diffusion calculation based on component homogenization approximation. In order to directly calculate the single-rod power of the whole core without introducing component homogenization approximation, the segmental SP 3 method. Full cor...

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Problems solved by technology

[0005] In order to solve the above-mentioned problems in the prior art, the purpose of the present invention is to provide a method for calculating the single-rod power of the whole reactor core, which can simultaneously deal with non-structural geometry and various common structural geometries, by minimizing the The approximation brought by lattice subdivision, the approximation introduced in the process of reducing numerical discreteness and iterative calculation, and the elimination of the approximation brought about by component homogenization and component power reconstruction provide high-precision single-rod power of the whole core, making up for the The disadvantage that the existing technology cannot give the results that meet the engineering precision

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