Title | Journal | Journal Categories | Citations | Publication Date |
---|---|---|---|---|
Analysis of several VERA benchmark problems with the photon transport capability of STREAM | Nuclear Engineering and Technology |
| 2 | 2022 |
Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS | Nuclear Engineering and Technology |
| 1 | 2021 |
Extension of Monte Carlo code MCS to spent fuel cask shielding analysis | International Journal of Energy Research |
| 4 | 2020 |
Initial MCNP6 release overview | Nuclear Technology |
| 2012 | |
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data | Nuclear Data Sheets |
| 1,884 | 2011 |