Monte Carlo codes such as MCNP and Geant4 rely on a combination of physics models and
evaluated nuclear data files (ENDF) to simulate the transport of neutrons through various …

To ensure the reliability of simulation tools, verification and comparison should be made
regularly. This paper describes the work performed in order to compare the neutron …

Temperature can strongly affect the probabilities of certain neutron interactions (fission,
capture, scattering, etc.) with materials. These probabilities are referred to in the nuclear …

A proper treatment of thermal neutron scattering requires accounting for chemical binding
through a scattering law S (α, β, T). Monte Carlo codes sample the secondary neutron …

An accurate description of interactions between thermal neutrons (below 4 eV) and
materials is key to simulate the transport of neutrons in a wide range of applications such as …

A comparison of the Monte Carlo based simulation codes MCNP6-1.0 and GEANT4-10.1 as
used for modelling large scale structures is presented here. The high-energy neutron field at …

Accurate representation of thermal neutron scattering in Monte Carlo transport simulations
requires that the molecular vibrations of the target material be accounted for. Historically, this …

A Monte Carlo program [1], which is a modified is such that the ZT direction coincideswith
the cylinder version of the code due to Bischoff [2], has recently axis. Thus the subroutine …

Convenient access to accurate nuclear data, particularly data describing low-energy
neutrons, is crucial for trustworthy simulations of thermal nuclear systems. Obtaining the …

Title of program: SLOW NEUTRON MULTIPLE SCATTERING Catalogue number: ACIC
Program obtainable from: CPC Program Library, Queen's University of Belfast, N. Ireland …