Implementation of an adaptive energy grid routine in NDEX for the processing of thermal neutron scattering cross sections

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

(2018) D.A. Brown et al.   NUCLEAR DATA SHEETS

The effects of nuclear data library processing on Geant4 and MCNP simulations of the thermal neutron scattering law

(2018) K. Hartling et al.   NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT

MC21 v.6.0 – A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilities

(2015) D.P. Griesheimer et al.   ANNALS OF NUCLEAR ENERGY

OpenMC: A state-of-the-art Monte Carlo code for research and development

(2015) Paul K. Romano et al.   ANNALS OF NUCLEAR ENERGY

The Serpent Monte Carlo code: Status, development and applications in 2013

(2015) Jaakko Leppänen et al.   ANNALS OF NUCLEAR ENERGY

Modern Techniques for Inelastic Thermal Neutron Scattering Analysis

(2014) A.I. Hawari   NUCLEAR DATA SHEETS

Comparison of thermal scattering processing options for S(α,β) cards in MCNP

(2013) Štefan Čerba et al.   ANNALS OF NUCLEAR ENERGY