We describe the new ENDF/B-VIII. 0 evaluated nuclear reaction data library. ENDF/B-VIII. 0
fully incorporates the new IAEA standards, includes improved thermal neutron scattering …

Monte Carlo methods are used for solving difficult stochastic problems in radiation shielding
applications. The aim of this paper is to show the possibility of using the Monte Carlo code …

The thermal neutron scattering cross-section of a solid depends on the energy (or
wavelength) of the incident neutrons. Devising a method to calculate the energy …

Novel neutron shielding material based on borated high-density polyethylene (HDPE) was
prepared in this study. In order to enhance the shielding efficacy of borated HDPE, nano …

Polymer composites offer an invaluable platform for neutron shielding applications,
however, the poor compatibility between the matrix and filler may compromise the physico …

Experimental protocols aiming at the characterisation of glass transition often suffer from
ambiguity. The ambition of the present study is to describe the glass transition in a complex …

We present a full set of procedures to evaluate the experimental corrections needed to
derive physically meaningful quantities from the measured neutron intensities in inelastic …

Occupational radiation protection should be applied to the design of treatment rooms for
various radiation therapy techniques, including BNCT, where escaping particles from the …

In this manuscript, the design process and genetic algorithm coupled with the SuperMC to
design the gradient composite radiation shielding material are described. As nuclear …

This work presents the total cross sections of a set of normal and deuterated alcohols
(hydrogenous 1-and 2-propanol and n-butanol, 1-propanol (OD) and fully deuterated 2 …