A method for coupled calculation of transport burnup for nuclear reactors

Abstract

The invention discloses a method suitable for the transportation burnup coupling calculation of a nuclear reactor. The method comprises the following steps that: 1: carrying out transportation calculation on the nucleus concentration of burnup step initiation to obtain a coarse mesh parameter and a microcosmic reaction rate; 2: carrying out burnup calculation by the microcosmic reaction rate and the nucleus concentration to obtain the nucleus concentration estimated by a burnup step end; 3: carrying out the transportation calculation by the estimated nucleus concentration to obtain the coarse mesh parameter and the microcosmic reaction rate; 4: dividing burnup CMFD (Coarse Mesh Finite Difference) substeps in a burnup step, and carrying out linear interpolation on the stored coarse mesh parameter; 5: updating the microcosmic reaction rate of the burnup CMFD substeps by the coarse mesh parameter obtained in the 4 and thin mesh neutron flux in the 3; 6: carrying out the burnup calculation by the microcosmic reaction rate on the burnup CMFD substeps to obtain the accurate nucleus concentration of the burnup step end; and 7: judging whether a burnup step number is consistent with an input value or not to judge whether calculation is finished or not. By use of the method, on a premise that extremely high accuracy is guaranteed, the step length of the burnup calculation is extremely enlarged, and calculation time in the whole service life of the nuclear reactor is shortened.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor physical calculations, in particular to a method suitable for coupling calculation of transport fuel consumption of nuclear reactors. Background technique [0002] Today, as the requirements for design conditions and calculation accuracy continue to increase, the field of nuclear reactor design hopes to achieve high-fidelity reactor physical calculations through accurate modeling and minimize the approximation and errors introduced in the calculation process of upstream nuclear reactors. Analyze simulations. [0003] High-fidelity reactor physics calculation mainly includes two parts: neutron transport calculation and burnup calculation. The neutron transport calculation obtains the neutron flux density field based on the nuclear density field, temperature field, etc., and then provides the power distribution of the core; The nuclear density field is iterated continuously in this way, an...

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Problems solved by technology

[0007] In the traditional transport burnup coupling strategy, when components or cores are full of poisons, the step size of burnup must be controlled at a small value to obtain an ideal result, but it also requires many times of neutron transport. calculation, which is extremely time-consuming in actual high-fidelity reactor physics calculations, greatly prolonging the calculation time

[0008] The estimation and correction method has high accuracy in the calculation of conventional fuel assemblies without burnable poison rods, but in the calculation of fuel assemblies with burnable poison rods and even the core, in order to ensure the accuracy of the estimation and correction method, it is necessary to use Divide finer fuel consumption steps, so in the fuel consumption calculation of the entire life cycle, multiple transportation calculations will be performed, which greatly increases the calculation time

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