Study of the Reduction of Neutron Flux Through the Iron Material Using GEANT4 Simulations

Abstract

Monte Carlo simulations using GEANT4 are performed to study the total neutron-nucleus cross section using a $C{f}^{252}$ source. The neutron flux with and without the iron foil for three different thicknesses is recorded on the scoring mesh volume using the primitive scorer named flatSurfaceFlux. The transmission method is used to calculate the neutron cross-section. The High Precision (QGSP BERT HP) neutron model, which is based on the G4NDL and ENDF-VI databases, is used for the hadronic interactions of low-energy neutrons below 20 MeV. The results are compared with the experimental data and nuclear reaction TALYS 1.96 code, and it is found that the GEANT4 results describe the experimental quite well. This study leads to useful insights into the mechanisms of neutron-induced reactions, particularly in the vicinity of the reactor domain for medium nuclei.

Keywords:

• Neutron-nucleus cross section
• Monte Carlo simulations using GEANT4
• QGSP BERT HP
• TALYS 1.9 code

Disclosure statement

No potential conflict of interest was reported by the author(s).