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Neutron shielding simulations by using GEANT4 and PHITS code are performed.As a neutron source, $^{252}$Cf is considered and the energy distribution ofthe neutrons emitted from $^{252}$Cf is assumed the Watt fission spectrum. Theneutron dose equivalent rates with and without the shield are estimated forshielding materials such as graphite, iron, polyethylene, NS-4-FR andKRAFTON-HB. For the neutron shielding simulations by using GEANT4, highprecision (G4HP) model with G4NDL 4.2 based on ENDF-VII data are used. And forPHITS simulations, JENDL-4.0 library are used for the same purpose. It is foundthat differences between the shielding calculations by using GEANT4 with G4NDL4.2 and PHITS with JENDL-4.0 library are not significant for all casesconsidered in this work. We investigate the accuracy of the neutron doseequivalent rates obtained from GEANT4 and PHITS by comparing our simulationresults with experimental data and other values calculated earlier. Calculatedneutron dose equivalent rates agree well with the experimental dose equivalentrates within 20% errors except for polyethylene. For polyethylene material,discrepancy between the calculations and the experiments are up to 40% but allsimulations show consistent features.

GEANT4 and PHITS simulations of the shielding of neutrons from $^{252}$Cf source