Skip to content
Research Article Open access CC BY 4.0

Simulation of Low Energy Neutron Shielding by GEANT4 and MCNP4C Code

Gh. Forozani, E. Ebrahimi

Current Journal of Applied Science and Technology · pp. 1–5 · Published 5 Feb 2016

10.9734/BJAST/2016/19827

Abstract

In this work neutrons shielding of 252Cf source simulated with GEANT4 program and MCNP4C code. The relative neutron flux rates are calculated for different materials. Among various physics models of GEANT4 for the hadronic interaction of neutron, we have used the High Precision (HP) model, which is based on the ENDF-V1 data and is able to treat elastic scattering, inelastic scattering, fission, fusion and capture. The simulation results of GEANT4 are compared with the results of MCNP4C.

Neutron shielding simulation Geant4 MCNP4C.

Cited by 2

Fabrication and characterization of rubcrete-iron composite for mixed radiation shielding

Lawrence Otieno Ochieng, N. O. Hashim, J. Kebwaro · AIP Advances · 2024

Article metrics

Real usage data collected on this platform.

0

Page views

0

PDF downloads

0

Outbound clicks

2

Citations

Views by country

Approximate, from request IP at view time — not citizenship or institution. Countries with fewer than 5 views are grouped as "Other".

No views recorded yet.

Traffic sources

Referring site, by host.

No traffic recorded yet.

Views and downloads exclude known bots/crawlers. Citations combines this platform's own DOI-resolved index with each external source's own reported total — see Cited by above for individually listed citing works. Last refreshed 0 seconds ago.