Primary Radiation Damage in Materials. Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade …

K Nordlund, AE Sand, F Granberg, SJ Zinkle, R Stoller… - 2015 - inis.iaea.org
Executive summary One of the consequences of the interaction of high energy particles
(photons, neutrons, ions or electrons) with crystalline materials is the formation of lattice …

Determination of mass attenuation coefficient for some polymers using Monte Carlo simulation

VP Singh, SP Shirmardi, ME Medhat, NM Badiger - Vacuum, 2015 - Elsevier
Mass attenuation coefficient, μ/ρ for some polymers with potential applications in dosimetry,
and medical physics has been calculated using Monte Carlo simulation code, MCNP-4C at …

Determination of gamma-ray shielding properties for silicate glasses containing Bi2O3, PbO, and BaO

R Bagheri, AK Moghaddam, SP Shirmardi… - Journal of Non …, 2018 - Elsevier
The mass attenuation coefficients (μ m), effective atomic cross section (σ a), effective atomic
number (Z eff) and effective electron density (N eff) of silicate glasses containing different …

Effectiveness of serpentine concrete as shielding material for neutron source facility using Monte Carlo code

RG Abrefah, K Tuffour-Achampong… - … and Technology of …, 2023 - Wiley Online Library
In recent years, much attention has been dedicated to finding techniques to reduce
exposure doses. This work examines the effectiveness of using serpentine concrete to …

Comparison of photon attenuation coefficients of various barite concretes and lead by MCNP code, XCOM and experimental data

SP Shirmardi, M Shamsaei, M Naserpour - Annals of Nuclear Energy, 2013 - Elsevier
In this study shielding properties of various barites concretes and lead in three high gamma
energies 0.662, 1.173, and 1.332 MeV were investigated using the MCNP-4C code and …

Introduction of graphene/h-BN metamaterial as neutron radiation shielding by implementing Monte Carlo simulation

M Hassanpour, M Hassanpour, S Faghihi… - Materials, 2022 - mdpi.com
In this paper, graphene/h-BN metamaterial was investigated as a new neutron radiation
shielding (NRS) material by Monte Carlo N-Particle X version (MCNPX) Transport Code …

Determining the mass attenuation coefficients for some polymers using MCNP code: a comparison study

SM Vahabi, M Bahreinipour, MS Zafarghandi - Vacuum, 2017 - Elsevier
In this study, the mass attenuation coefficient for some polymers has been determined using
MCNP4C code. The simulation results were compared with available experimental data and …

Analysis by Monte Carlo methods of the response of an extended-range Bonner Sphere Spectrometer

R García-Baonza, GF García-Fernández… - Applied Radiation and …, 2020 - Elsevier
High-energy neutrons up to 230 MeV are generated as a consequence of (p, n) nuclear
reactions in proton therapy facilities. The aim of this work is to evaluate the potential …

Effective atomic number and buildup factor calculations for metal nano particle doped polymer gel

P Sathiyaraj, EJJ Samuel, CCS Valeriano, M Kurudirek - Vacuum, 2017 - Elsevier
The present study aimed at verifying the water equivalency of the PAGAT gel and metal
nano particle (different concentration of gold and silver) PAGAT (MPAGAT) gel in terms of …

Neutron and gamma flux distributions and their implications for radiation damage in the shielded superconducting core of a fusion power plant

CG Windsor, JG Morgan - Nuclear Fusion, 2017 - iopscience.iop.org
The neutron and gamma ray fluxes within the shielded high-temperature superconducting
central columns of proposed spherical tokamak power plants have been studied using the …