| An improved genetic algorithm approach to the unit commitment/economic dispatch problem R Ponciroli, NE Stauff, J Ramsey, F Ganda, RB Vilim IEEE Transactions on Power Systems 35 (5), 4005-4013, 2020 | 57 | 2020 |
| AEN-WPRS Sodium Fast Reactor Core Definitions (version 1.2-September 19th) D Blanchet, L Buiron, N Stauff, TK Kim, T Taiwo Organisation for Economic Co-operation and Development/Nuclear Energy Agency, 2011 | 43* | 2011 |
| Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems NR Brown, JJ Powers, B Feng, F Heidet, NE Stauff, G Zhang, M Todosow, ... Nuclear Engineering and design 289, 252-265, 2015 | 35 | 2015 |
| Introduction to the nuclear energy advanced modeling and simulation workbench BT Rearden, RA Lefebvre, AB Thompson, BR Langley, NE Stauff M&C 2017–International Conference on Mathematics & Computational Methods …, 2017 | 28 | 2017 |
| Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors K Zeng, NE Stauff, J Hou, TK Kim Progress in Nuclear Energy 120, 103184, 2020 | 27* | 2020 |
| Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor C Fiorina, NE Stauff, F Franceschini, MT Wenner, A Stanculescu, TK Kim, ... Annals of Nuclear Energy 62, 26-39, 2013 | 26 | 2013 |
| Variations in nuclear waste management performance of various fuel-cycle options NE Stauff, TK Kim, TA Taiwo Journal of Nuclear Science and Technology 52 (7-8), 1058-1073, 2015 | 23 | 2015 |
| Neutronic design and analysis of the holos-quad concept N Stauff, C Lee, P Shriwise, Y Miao, R Hu, P Vegendla, T Fei Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 21 | 2019 |
| Benchmark for neutronic analysis of sodium-cooled fast reactor cores with various fuel types and core sizes NE Stauff, TK Kim, TA Taiwo, L Buiron, G Rimpault, E Brun, YK Lee, ... Organisation for Economic Co-Operation and Development, 2016 | 21 | 2016 |
| Investigating benefits and challenges of converting retiring coal plants into nuclear plants JK Hansen, WD Jenson, AM Wrobel, N Stauff, K Biegel, TK Kim, R Belles, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2022 | 18 | 2022 |
| Fuel performance evaluation of annular metallic fuels for an advanced fast reactor concept Y Miao, N Stauff, A Oaks, AM Yacout, TK Kim Nuclear Engineering and Design 352, 110157, 2019 | 18 | 2019 |
| Improved Reactivity Worth Estimation of MC2-3/DIF3D in Fast Reactor Analysis NES C. H. Lee ANS Summer Meeting, 2015 | 18* | 2015 |
| Detailed analyses of a TRISO-fueled microreactor: Modeling of a Micro-Reactor System using NEAMS Tools N Stauff, K Mo, Y Cao, J Thomas, Y Miao, L Zou, D Nunez, E Shemon, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 16 | 2021 |
| Status of the NEAMS and ARC neutronic fast reactor tools integration to the NEAMS Workbench N Stauff, P Lartaud, YS Jung, CH Lee, K Zeng, J Hou Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 14 | 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 |
| Evaluation of Large 3600MWth Sodium-cooled Fast Reactor OECD Neutronic Benchmarks L Buiron, G Rimpault, B Fontaine, TK Kim, NE Stauff, TA Taiwo, A Yamaji, ... PHYSOR2014, 2014 | 13 | 2014 |
| Comparative review on different fuels for GEN IV Sodium Fast Reactors: Merits and drawbacks F Varaine, N Stauff, M Masson, M Pelletier, G Mignot, G Rimpault, ... | 13 | 2009 |
| Multi-criteria methodology to design a sodium-cooled carbide-fueled GEN-IV reactor N Stauff Paris XI Univ.(France), 2011 | 12* | 2011 |
| Resolution of proliferation issues for a sodium fast reactor blanket NE Stauff, MJ Driscoll, B Forget, P Hejzlar Nuclear Technology 170 (3), 371-382, 2010 | 12 | 2010 |
| Uncertainty quantification of ABR transient safety analysis-nuclear data uncertainties N Stauff, K Zeng, G Zhang, G Aliberti, J Hou, T Fanning, TK Kim Proceedigs of the Best Estimate Plus Uncertainty (BEPU), 2018 | 11 | 2018 |
Roberto PonciroliPrincipal Nuclear Engineer, Argonne National LaboratoryVerified email at anl.gov
