The application relates to the technical field of medical
data processing, and discloses a macroscopic cross-section
database construction method, a
dose determination method, a device and equipment, which comprises the following steps: setting multiple
boron concentration values for the tissue types corresponding to a
human body model; selecting corresponding
neutron source parameters for the tissue types and the multiple
boron concentration values, wherein the
neutron source parameters comprise energy range values; dividing the energy range values into multiple discrete
neutron energy groups; performing
particle transport simulation based on the selected
neutron source parameters,
jumping between different neutron energy groups in the
simulation process, and obtaining neutron reaction rates and neutron fluxes of the tissue types under the multiple
boron concentration values and the multiple neutron energy groups; and obtaining neutron macroscopic cross-section values of the tissue types under the multiple
boron concentration values and the multiple neutron energy groups based on the neutron reaction rates and the neutron fluxes, and constructing a multi-group macroscopic cross-section
database. The application can improve the calculation efficiency of the
radiation dose and improve the adaptability to individual metabolic differences during
dose calculation.