Data for: Analysis of VVER-1000 Mock-up Criticality Experiments with Nuclear Data Library ENDF/B-VIII.0 and Monte Carlo code MCS

Published: 20 August 2020| Version 1 | DOI: 10.17632/xsb3sjsdwz.1
Deokjung Lee, Fathurrahman Setiawan, Matthieu Lemaire


This research data contains 12 inputs: 6 for the Monte Carlo code MCNP (developed at Los Alamos, New Mexico) and 6 for the Monte Carlo code MCS (developed at UNIST, South Korea). For each code, the inputs are criticality calculations modelling 6 different critical configurations of the VVER-1000 mock-up. All the inputs correspond to the reference calculations without sensivity analysis / perturbations (all the values of parameters are nominal). All the inputs use the ENDF/B-VII.1 library. The inputs are included as supplementary material with the hope that they are useful for the interpretation of VVER-1000 mock-up benchmarks, but without any warranty.



Nuclear Engineering