| Candidate core designs for the transformational challenge reactor BJ Ade, BR Betzler, AJ Wysocki, MS Greenwood, PC Chesser, KA Terrani, ... Journal of Nuclear Engineering 2 (1), 74-85, 2021 | 36 | 2021 |
| Advanced manufacturing for nuclear core design BR Betzler, BJ Ade, AJ Wysocki, MS Greenwood, JJW Heineman, ... EPJ Web of Conferences 247, 01011, 2021 | 28 | 2021 |
| A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power B Ye, GL Hofman, A Leenaers, A Bergeron, V Kuzminov, ... Journal of Nuclear Materials 499, 191-203, 2018 | 28 | 2018 |
| Review of the Oak Ridge National Laboratory (ORNL) neutronic calculations regarding the conversion of the high flux isotope reactor (HFIR) to the use of low enriched uranium … A Bergeron Argonne National Lab.(ANL), Argonne, IL (United States), 2013 | 22 | 2013 |
| US high performance research reactor conversion program: An overview on element design EH Wilson, A Bergeron, JA Stillman, TA Heltemes, D Jaluvka, L Jamison European Research Reactor Conference,” Rotterdam, Netherlands, 2017 | 20 | 2017 |
| Comparison and validation of HEU and LEU modeling results to HEU experimental benchmark data for the Massachusetts Institute of Technology MITR reactor. EH Wilson, TH Newton, A Bergeron, N Horelik, JG Stevens Argonne National Lab.(ANL), Argonne, IL (United States), 2010 | 17 | 2010 |
| Comparison and validation of HEU and LEU modeling results to HEU experimental benchmark data for the Massachusetts Institute of Technology MITR reactor. EH Wilson, TH Newton, A Bergeron, N Horelik, JG Stevens Argonne National Lab.(ANL), Argonne, IL (United States), 2010 | 17 | 2010 |
| Low enriched uranium core design for the massachusetts institute of technology reactor (mitr) with un-finned 12 mil-thick clad umo monolithic fuel A Bergeron, EH Wilson, G Yesilyurt, FD Dunn, JG Stevens, LW Hu, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2013 | 15 | 2013 |
| Conceptual design of the transformational challenge reactor BR Betzler, BJ Ade, PK Jain, AJ Wysocki, PC Chesser, WM Kirkland, ... Nuclear Science and Engineering 196 (12), 1399-1424, 2022 | 14 | 2022 |
| Improuvement of the conversion ration in PWR,“ F Damian, S Douce, A Bergeron, B Gastaldi, A Conti, F Moutin, D Pialla Physor, Pittsburg, Pennsylvania, 2010 | 13 | 2010 |
| Evaluation of measurements performed on the French high flux reactor (RHF) Y Calzavara, S Fuard, A Bergeron RHF-HWR-RESR-001 CRIT, International Handbook of Evaluated Reactor Physics …, 2009 | 10 | 2009 |
| Transformational Challenge Reactor Moderator Material Selection to Achieve Fuel Minimization A Bergeron, P Vegendla, S Mohanty, F Heidet, BJ Ade, BR Betzler Transactions of the American Nuclear Society 122, 2020 | 9 | 2020 |
| Thermal properties for the thermal-hydraulics analyses of the BR2 maximum nominal heat flux B Dionne, A Bergeron, JR Licht, YS Kim, GL Hofman Argonne National Lab.(ANL), Argonne, IL (United States), 2015 | 9 | 2015 |
| Neutronics Conversion Analyses of the Laue-Langevin Institute (ILL) High Flux Reactor (RHF) A Bergeron, B Dionne, Y Calzavara Argonne National Lab.(ANL), Argonne, IL (United States), 2014 | 9 | 2014 |
| Advanced high conversion pwr: preliminary analysis H Golfier, V Bellanger, A Bergeron, F Dolci, B Gastaldi, O Koberl, ... | 9 | 2007 |
| Control Element Design for the Transformational Challenge Reactor (TCR) J Burns, B Betzler, B Ade, F Heidet, A Bergeron Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2020 | 6 | 2020 |
| Neutronic Analyses for HEU to LEU Fuel Conversion of the Massachusetts Institute of Technology MITR Reactor TH Newton Jr, EH Wilson, A Bergeron, N Horelik, JG Stevens ANL/RERTR/TM-10-40, Argonne National Laboratory, 2010 | 6 | 2010 |
| Temperature effects on interdiffusion of Al and U-Mo under irradiation B Ye, Y Miao, J Shi, D Salvato, K Mo, L Jamison, A Bergeron, GL Hofman, ... Journal of Nuclear Materials 544, 152684, 2021 | 5 | 2021 |
| Involute Working Group–Validation of CFD Turbulence Models for Steady-State Safety Analysis C Bojanowski, A Bergeron, J Licht Argonne National Lab.(ANL), Argonne, IL (United States), 2020 | 5 | 2020 |
| Involute Working Group–Progress towards Validation of CFD for Involute-Plate Reactors Safety Analysis A Bergeron, C Bojanowski, J Licht, K Shehu, C Reiter, F Thomas, ... RERTR 2019, 40th International Meeting on Reduced Enrichment for Research …, 2019 | 5 | 2019 |
