| Categorization of used nuclear fuel inventory in support of a comprehensive national nuclear fuel cycle strategy J Wagner | 33 | 2012 |
| Advancing the Fork detector for quantitative spent nuclear fuel verification S Vaccaro, IC Gauld, J Hu, P De Baere, J Peterson, P Schwalbach, ... Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2018 | 26 | 2018 |
| Estimation of inherent safety margins in loaded commercial spent nuclear fuel casks K Banerjee, KR Robb, G Radulescu, JM Scaglione, JC Wagner, JB Clarity, ... Nuclear Technology 195 (2), 124-142, 2016 | 24 | 2016 |
| Integrated data and analysis system for commercial used nuclear fuel safety assessments–14657 J Scaglione, J Peterson, K Banerjee, K Robb, R LeFebvre WM2014 Conference, 2014 | 22 | 2014 |
| US Commercial Spent Nuclear Fuel Assembly Characteristics-1968-2013 J Hu, JL Peterson, IC Gauld, SM Bowman Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016 | 20 | 2016 |
| Calculation of heating values for the high flux isotope reactor J Peterson, G Ilas International Conference on the Physics of Reactors 2012: Advances in …, 2012 | 15 | 2012 |
| Modeling spent TRISO fuel for geological disposal: corrosion and failure under oxidizing conditions in the presence of water JL Peterson, ML Dunzik-Gougar Progress in Nuclear Energy 53 (3), 278-284, 2011 | 14 | 2011 |
| Development of streamlined nuclear safety analysis tool for spent nuclear fuel applications RA Lefebvre, P Miller, JM Scaglione, K Banerjee, JL Peterson, ... Nuclear Technology 199 (3), 227-244, 2017 | 13 | 2017 |
| The multi-step cadis method for shutdown dose rate calculations and uncertainty propagation AM Ibrahim, DE Peplow, RE Grove, JL Peterson, SR Johnson Nuclear Technology 192 (3), 286-298, 2015 | 13 | 2015 |
| Fuel Cycle Analysis of Thermal and Fast Spectrum Molten Salt Reactors BR Betzler, J Powers, JL Peterson-Droogh, A Worrall Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017 | 11 | 2017 |
| Used Nuclear Fuel Storage Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) J Peterson, R Lefebvre, H Smith, D Ilas, K Robb, TE Michener, H Adkins, ... FCRD-NFST-2013-000117 Rev. 0, US Department of Energy Nuclear Fuels Storage …, 2013 | 11 | 2013 |
| A methodology for uncertainty quantification and sensitivity analysis for responses subject to Monte Carlo uncertainty with application to fuel plate characteristics in the ATRC D Price, A Maile, J Peterson-Droogh, D Blight Nuclear Engineering and Technology 54 (3), 790-802, 2022 | 10 | 2022 |
| Standardized verification of the Cyclus fuel cycle simulator JW Bae, JL Peterson-Droogh, KD Huff Annals of Nuclear Energy 128, 288-291, 2019 | 10 | 2019 |
| Unf-st&dards unified database and the automatic document generator J Peterson, B Van Den Akker, R Cumberland, P Miller, K Banerjee Nuclear Technology 199 (3), 310-319, 2017 | 10 | 2017 |
| Novel hybrid Monte Carlo/deterministic technique for shutdown dose rate analyses of fusion energy systems AM Ibrahim, DE Peplow, JL Peterson, RE Grove Fusion Engineering and Design 89 (9-10), 1933-1938, 2014 | 9 | 2014 |
| Agenda for socio-economic life-cycle research JL Peterson J. Econ. Bus.;(United States) 32 (2), 1980 | 8 | 1980 |
| Current neutronic calculation techniques for modeling the production of Ir-192 in HFIR JL Peterson-Droogh, RH Howard Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2018 | 7 | 2018 |
| Transition Analysis of Promising US Future Fuel Cycles Using ORION EE Sunny, A Worrall, JL Peterson, JJ Powers, JC Gehin, R Gregg Oak Ridge National Laboratory (ORNL), 2015 | 6 | 2015 |
| Data Identification and Verification for Waste Management System Analyses B van den Akker, J Jarrell, J Peterson, R Joseph, I Busch, K Banerjee, ... FCRD-NFST-2014-000530 Rev. 0, 2014 | 6 | 2014 |
| ORIGAMI Automator Primer: Automated ORIGEN Source Terms and Spent Fuel Storage Pool Analysis WA Wieselquist, AB Thompson, JL Peterson, SM Bowman ORNL/TM-2015/409, Oak Ridge National Laboratory, 2016 | 5 | 2016 |
