Background: In recent years, there has been an increased interest toward non-lead radiation shields consisting of small-sized filler particles doped into polymer matrices. In this paper, we study a new polyvinyl alcohol (PVA)/WO3 composite in the presence of high-energy gamma photons through simulation via the Monte Carlo N-Particle (MCNP) simulation code. Materia...

Abstract The Cs 2 LiYCl 6 :Ce crystal (CLYC) is an inorganic scintillator which has been developed for the γ-ray and neutron measurement with high detection efficiency, resolution, no need unfolding technique. To enhance of fast neutron, CLYC 7 Li-enrichment (CLYC7) developed. In this work, response CLYC7 detector to obtained using 137 calibration source calculated Monte Carlo N-Particle transp...

Prediction of neutron flux at the irradiation devices of a research reactor facility is essential for the design and evaluation of experiments involving material irradiations. A computational model of the Greek Research Reactor (GRR-1) was developed using the Monte Carlo code MCNP with continuous energy neutron cross-section data evaluations from ENDF/B-VI library. The model included detailed g...

A new algorithm for energy-loss straggling in MCNP is demonstrated. An approximate but accurate energy-loss moment-preserving differential cross section is used in conjunction with single event Monte Carlo simulation through each condensed history step to show that highly accurate energy spectra, leakage currents, and dose profiles can be obtained. This new approach provides a viable and even p...

In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling Simulation (NEAMS)Workbench. Specifically, enhance user interface of each code by developing full-featured editor services. Next, re-define textual outputs in HDF5 formats, at great convenience to user. Further, these are (optionally) coerced OpenMC format, enabling pow...