Method for calculating thermal neutron scattering cross section of dispersion type fuel and related device

By constructing and calculating the supercell of diffuse fuel and accurately calculating its thermal neutron scattering cross-section, the problem of insufficient calculation accuracy in the existing technology is solved, the theoretical basis of reactor design and optimization is improved, and the safe operation of the reactor is ensured.

CN119885619AActive Publication Date: 2025-04-25XI AN JIAOTONG UNIV
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Patent Information

Application Number
CN202411951601.0
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2024-12-27
Publication Date
2025-04-25
Estimated Expiration
2044-12-27

AI Technical Summary

Technical Problem

It is difficult for the prior art to accurately calculate the thermal neutron scattering cross-section data of new materials such as U3Si2-Al diffuse fuels, affecting the theoretical basis for reactor design, optimization and operation.

Method used

By constructing a supercell of diffuse fuel, the Hellmann-Feynman forces between each atom of the supercell are calculated, and the phonon state density, mean square displacement matrix, dispersion relationship and polarization vector are calculated based on these forces, and the thermal neutron scattering cross-section is then calculated. Combining experimental measurement data, correct the calculation input parameters to improve the calculation accuracy.

Benefits of technology

The accurate calculation of the thermal neutron scattering cross-section data of the new diffused fuel is achieved, the theoretical basis of reactor design and optimization is improved, and the safe operation of the reactor is ensured.

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Abstract

The invention discloses a thermal neutron scattering cross section calculation method of dispersion type fuel and a related device, and belongs to the technical field of reaction cross section calculation of materials in a reactor. The method comprises the following steps: firstly, constructing a supercell of the dispersion type fuel, and calculating Hellmann-Feynman force between atoms of the supercell; calculating a phonon state density, a mean square displacement matrix, a dispersion relation and a polarization vector according to the Hellmann-Feynman force; abundant input information is provided for thermal neutron scattering law data calculation of reactor materials, the precision of thermal neutron scattering law calculation can be improved, and then a thermal neutron scattering cross section theoretical value is obtained through calculation; and finally, comparing an actual experimental measurement value with the theoretical value of the thermal neutron scattering cross section, correcting an input parameter of thermal neutron scattering calculation according to an error between the actual experimental measurement value and the theoretical value of the thermal neutron scattering cross section, and then obtaining a dispersion type fuel thermal neutron scattering cross section library with higher precision again through the corrected input parameter, so that compared with the prior art, the calculation result is more accurate.
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Citation Information

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