| Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core D Rochman, O Leray, M Hursin, H Ferroukhi, A Vasiliev, A Aures, ... Nuclear Data Sheets 139, 1-76, 2017 | 64 | 2017 |
| Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X A Aures, F Bostelmann, M Hursin, O Leray Annals of Nuclear Energy 101, 262-269, 2017 | 29 | 2017 |
| Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE F Bostelmann, G Strydom Annals of Nuclear Energy 110, 317-329, 2017 | 27 | 2017 |
| SCALE capabilities for high temperature gas-cooled reactor analysis F Bostelmann, C Celik, ML Williams, RJ Ellis, G Ilas, WA Wieselquist Annals of Nuclear Energy 147, 107673, 2020 | 26 | 2020 |
| Uncertainty and sensitivity analysis in criticality calculations with perturbation theory and sampling F Bostelmann, FP Weiss, A Aures, K Velkov, W Zwermann, BT Rearden, ... ANS MC2015, Nashville, TN, USA, 2015 | 20 | 2015 |
| Modeling of the molten salt reactor experiment with SCALE F Bostelmann, SE Skutnik, ED Walker, G Ilas, WA Wieselquist Nuclear Technology 208 (4), 603-624, 2022 | 19 | 2022 |
| Key nuclear data impacting reactivity in advanced reactors F Bostelmann, G Ilas, WA Wieselquist Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 18 | 2020 |
| SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis R Bostelmann, C Celik, RF Kile, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2022 | 17 | 2022 |
| Sampling-Based Nuclear Data Uncertainty Analysis in Criticality and Depletion Calculations F Bostelmann, W Zwermann, B Krzykacz-Hausmann, L Gallner, A Aures, ... Proceedings of the ANS MC2015, Nashville, TN, USA, 19-23, 2015 | 17 | 2015 |
| Criticality calculations of the very high temperature reactor critical assembly benchmark with serpent and SCALE/KENO-VI F Bostelmann, HR Hammer, J Ortensi, G Strydom, K Velkov, W Zwermann Annals of Nuclear Energy 90, 343-352, 2016 | 16 | 2016 |
| Results for Phase I of the IAEA coordinated research program on HTGR uncertainties G Strydom, F Bostelmann, SJ Yoon Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 16 | 2015 |
| Nuclear Data Assessment for Advanced Reactors R Bostelmann, G Ilas, C Celik, AM Holcomb, WA Wieselquist Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021 | 15 | 2021 |
| Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors F Bostelmann, AM Holcomb, JB Clarity, WBJ Marshall, V Sobes, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 15 | 2019 |
| The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results F Bostelmann, G Strydom, F Reitsma, K Ivanov Nuclear Engineering and Design 306, 77-88, 2016 | 15 | 2016 |
| The IAEA coordinated research program on HTGR uncertainty analysis: phase I status and initial results F Reitsma, G Strydom, F Bostelmann, K Ivanov Proceedings of HTR, 2014 | 15 | 2014 |
| Reactor simulations with nuclear data uncertainties A Aures, W Bernnat, F Bostelmann, J Bousquet, B Krzykacz-Hausmann, ... Nuclear Engineering and Design 355, 110313, 2019 | 13 | 2019 |
| Objectives and Status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM) G Rimpault, L Buiron, N Stauff, TK Kim, TA Taiwo, YK Lee, A Aures, ... International Conference on Fast Reactors and Related Fuel Cycles (FR-2017), 2017 | 13 | 2017 |
| About the Impact of the Unresolved Resonance Region in Monte Carlo Simulations of Sodium Fast Reactors A Jiménez-Carrascosa, E Fridman, N García-Herranz, F Alvarez-Velarde, ... Proceedings of the International Congress on Advances in Nuclear Power …, 2019 | 12 | 2019 |
| Uncertainty in the delayed neutron fraction in fuel assembly depletion calculations A Aures, F Bostelmann, IA Kodeli, K Velkov, W Zwermann EPJ Web of Conferences 146, 02052, 2017 | 12 | 2017 |
| Two-step neutronics calculations with Shift and Griffin for advanced reactor systems TM Pandya, F Bostelmann, M Jessee, J Ortensi Annals of Nuclear Energy 173, 109131, 2022 | 11 | 2022 |
