| A statistical sampling method for uncertainty analysis with SCALE and XSUSA ML Williams, G Ilas, MA Jessee, BT Rearden, D Wiarda, W Zwermann, ... Nuclear technology 183 (3), 515-526, 2013 | 132 | 2013 |
| Fuel cycle advantages and dynamics features of liquid fueled MSR J Křepel, B Hombourger, C Fiorina, K Mikityuk, U Rohde, S Kliem, A Pautz Annals of Nuclear Energy 64, 380-397, 2014 | 64 | 2014 |
| DORT-TD: A transient neutron transport code with fully implicit time integration A Pautz, A Birkhofer Nuclear science and engineering 145 (3), 299-319, 2003 | 60 | 2003 |
| Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform C Fiorina, N Kerkar, K Mikityuk, P Rubiolo, A Pautz Annals of Nuclear Energy 96, 212-222, 2016 | 58 | 2016 |
| Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor C Fiorina, M Hursin, A Pautz Annals of Nuclear Energy 101, 419-428, 2017 | 52 | 2017 |
| Nuclear data uncertainty propagation on spent fuel nuclide compositions O Leray, D Rochman, P Grimm, H Ferroukhi, A Vasiliev, M Hursin, ... Annals of Nuclear Energy 94, 603-611, 2016 | 49 | 2016 |
| The OFFBEAT multi-dimensional fuel behavior solver A Scolaro, I Clifford, C Fiorina, A Pautz Nuclear Engineering and Design 358, 110416, 2020 | 47 | 2020 |
| NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method T Zhu, A Vasiliev, H Ferroukhi, A Pautz Annals of Nuclear Energy 75, 713-722, 2015 | 37 | 2015 |
| Influence of nuclear data uncertainties on reactor core calculations M Klein, L Gallner, B Krzykacz-Hausmann, A Pautz, W Zwermann Kerntechnik 76 (3), 174-178, 2011 | 32 | 2011 |
| Uncertainty analyses with nuclear covariance data in reactor core calculations W Zwermann, B Krzykacz-Hausmann, L Gallner, A Pautz Annual meeting on nuclear technology 2010. Documentation, 2010 | 31 | 2010 |
| Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes–PREMIUM benchmark T Skorek, A de Crécy, A Kovtonyuk, A Petruzzi, R Mendizábal, ... Nuclear Engineering and Design 354, 110199, 2019 | 29 | 2019 |
| SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations D Chionis, A Dokhane, L Belblidia, M Pecchia, G Girardin, H Ferroukhi, ... Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science …, 2017 | 28 | 2017 |
| Kilogram‐Scale Crystallogenesis of Halide Perovskites for Gamma‐Rays Dose Rate Measurements P Andričević, P Frajtag, VP Lamirand, A Pautz, M Kollár, B Náfrádi, ... Advanced Science 8 (2), 2001882, 2021 | 27 | 2021 |
| A two-step approach to uncertainty quantification of core simulators A Yankov, B Collins, M Klein, MA Jessee, W Zwermann, K Velkov, A Pautz, ... Science and Technology of Nuclear Installations 2012, 2012 | 27 | 2012 |
| Future experimental programmes in the CROCUS reactor VP Lamirand, M Hursin, G Perret, P Frajtag, O Pakari, A Pautz Conference proceedings of RRFM/IGORR 2016, 284-292, 2016 | 26 | 2016 |
| Influence of nuclear covariance data on reactor core calculations W Zwermann, B Krzykacz-Hausmann, L Gallner, A Pautz Second International Workshop on Nuclear Data Evaluation for Reactor …, 2009 | 26 | 2009 |
| Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments D Siefman, M Hursin, D Rochman, S Pelloni, A Pautz The European Physical Journal Plus 133 (10), 429, 2018 | 25 | 2018 |
| Status of XSUSA for sampling based nuclear data uncertainty and sensitivity analysis W Zwermann, L Gallner, M Klein, B Krzykacz-Hausmann, I Pasichnyk, ... EPJ Web of Conferences 42, 03003, 2013 | 25 | 2013 |
| Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor DJ Siefman, G Girardin, A Rais, A Pautz, M Hursin Annals of Nuclear Energy 85, 434-443, 2015 | 24 | 2015 |
| Kalinin-3 Coolant Transient Benchmark Switching-off of One of the Four Operating Main Circulation Pumps at Nominal Reactor Power VA Tereshonok, SP Nikonov, MP Lizorkin, K Velkov, A Pautz, K Ivanov NEA/NSC/DOC (2009) 5. Final draft, 2009 | 23 | 2009 |
