Search

A Windows-based application software called EpiXS (available at https://www.pnri.dost.gov.ph/index.php/downloads/software/epixs) was constructed for photon attenuation, dosimetry and shielding, and is based on EPICS2017 of ENDF/B-VIII and EPDL97 of ENDF/B-VI.8. The software performs data library interpolation between 1 keV and 100 GeV and calculates partial or total cross sections (σ), mass attenuation coefficients (μ/ρ), linear attenuation coefficients (μ), mean free paths (mfp), half-value layers (hvl), effective atomic numbers (Z eff), electron densities (N eff), and the auxiliary parameters and buildup factors for energy absorption (EABF) and exposure (EBF) via Geometric-Progression, for any user-defined material. It has a user-friendly design and performs quick interactive graphing and data tabulations. Data generated by the software were compared with published results from literature as well as generated results from XCOM and from other programs based on XCOM/NIST libraries. The comparisons were mostly found to agree well, nonetheless the deviations observed may highlight the values from the latest EPICS2017. The EpiXS is introduced as a new tool for instant calculations involving ionizing photon radiation dosimetry and shielding. • Software was made for calculating σ, μ/ρ, ρ, mfp, hvl, Z eff , N eff , EABF and EBF. • All photon energies from 1 keV to 100 GeV can be interpolated. • X-ray absorption edge energies in EPICS2017 and EPDL97 can be viewed. • Data tables can be generated and exported as CSV for MS Excel. • Graphs can be exported as vector image EMF files. [ABSTRACT FROM AUTHOR]

A fast neutron mass removal cross sections (Σ R / ρ) database covering the elemental range of Z = 1 to 92 is generated for source neutron energy distributions based on 241Am–Be, 252Cf, and 235U. Monte Carlo simulations using ENDF/B-VIII.0 nuclear data were performed with the fast neutron removal theory's ideal spherical representation. The ENDF/B-VIII.0-based Σ R / ρ ′s derived were compared with values from the Oak Ridge National Laboratory's Lid Tank Shielding Facility (LTSF) experiments, values from software Phy-X/PSD and MRCsC, values obtained by an empirical model in Zoller, and values derived using the older ENDF/B-VII.0 nuclear data library. Subsequently, the generated Σ R / ρ ′s were evaluated for convergence under varying moderator thickness. Results indicate that the Σ R / ρ quantity for fission and (alpha, n) spectra is universal, with slight deviations for low Z elements. The Σ R / ρ values generated from ENDF/B-VIII.0 agreed with LTSF experiments with an average relative deviation of 8.58%. Moreover, using ENDF/B-VIII.0-based Σ R / ρ ′s, the derived fast neutron effective removal cross sections (Σ R 's) for several light compounds and dry concrete have better agreement on average with LTSF experiments compared with values derived from the available Σ R / ρ ′s in the literature. Significant differences were found for Σ R / ρ ′s that were generated with ENDF/B-VIII.0 as compared with the superseded ENDF/B-VII.0. Furthermore, ENDF/B-generated Σ R / ρ ′s through spherical model showed the expected convergence towards singular values at moderator thicknesses practical for fast neutron removal theory applications. Owing to the relatively high unavoidable uncertainties of the LTSF experimental Σ R / ρ ′s, the ENDF/B-VIII.0-based Σ R / ρ ′s present a new and potentially favorable database in Σ R general calculations for homogeneous multi-element materials for point-kernel shielding applications. • A Σ R / ρ database was produced using the latest ENDF/B via multi-layer sphere model. • Produced Σ R / ρ ′s led to calculated Σ R values close to LTSF experimental measurement. • All Σ R / ρ ′s for fission and (α,n) neutron source energy spectra were similar. • Differences were found in Σ R / ρ ′s produced using 7th and 8th versions of ENDF/B. • Convergence of Σ R / ρ ′s at increasing moderator thickness was demonstrated. [ABSTRACT FROM AUTHOR]