Nuclear data of importance to the operation of MYRRHA, a research infrastructure supporting the development of Generation-IV reactors, were identified by sensitivity analysis. The data recommended in the main nuclear data libraries (i.e. JEFF, JENDL, ENDF/B, and TENDL) were compared and...

The characterisation of Spent Nuclear Fuel (SNF) in view of intermediate storage and final disposal is discussed. The main observables of interest that need to be determined are the decay heat, neutron and g-ray emission spectra. In addition, the inventory of specific nuclides that are important...

Experimental data and evaluated data libraries related to neutron induced reaction cross sections for 238U in the resonance region are reviewed. Based on this review a set of test files is produced to study systematic effects such as the impact of the upper boundary of the resolved resonance...

Transmission measurements through metallic bismuth samples have been performed at the time-of-flight facility GELINA. The measurements have been carried out at a 50 m transmission station using a Li-glass scintillator with the accelerator operating at 400 Hz. This report provides the...

The quality of the capture cross sections in JEFF-3.2 for a selection of nuclides has been assessed in comparison to other evaluated nuclear data libraries (ENDF/B-VII.1, JENDL- 4.0, TENDL-2014 and IRDFF v1.05). The incident neutron capture reactions of this nuclides have been compared to...

A new evaluation of neutron induced reactions on 197Au nucleus in the energy regions below 500 eV and from 4 keV to 100 keV is presented. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluation with corresponding files from the ENDF/B-VII.1 library. The...

Transmission measurements have been performed at the time-of-flight facility GELINA to determine neutron resonance parameters for 51V. The measurements have been carried out at a 50 m transmission station at a moderated neutron beam using a Li-glass scintillator with the accelerator operating at...

Requirements to construct a compact Neutron Resonance Analysis system for the characterisation of nuclear materials are described. The design of the system is focussed on the characterisation of melted fuel formed in a severe nuclear accident. The requirements are based on results of previous...

Measurements have been performed at the time-of-flight facility GELINA to determine the total cross section for neutron induced reactions in natCe. The measurements have been carried out at the 50 m transmission station at a moderated neutron beam using a Li-glass scintillator with the...

A compact system for Neutron Resonance Analysis has been studied based on results of simulations. The influence of the moderator characteristics of the neutron producing target on both the neutron emission spectrum and the time-of-flight response functions has been investigated. Results obtained...