| Isotopic depletion and decay methods and analysis capabilities in SCALE IC Gauld, G Radulescu, G Ilas, BD Murphy, ML Williams, D Wiarda Nuclear Technology 174 (2), 169-195, 2011 | 233 | 2011 |
| 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 |
| SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data F Michel-Sendis, I Gauld, JS Martinez, C Alejano, M Bossant, ... Annals of Nuclear Energy 110, 779-788, 2017 | 103 | 2017 |
| Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE G Ilas, IC Gauld, G Radulescu Annals of Nuclear Energy 46, 43-55, 2012 | 72 | 2012 |
| SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions G Radulescu, IC Gauld, G Ilas ORNL/TM-2010/44, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 2010 | 62 | 2010 |
| Modeling and simulations for the high flux isotope reactor cycle 400 G Ilas, D Chandler, BJ Ade, EE Sunny, BR Betzler, D Pinkston Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2015 | 56 | 2015 |
| Fuel age impacts on gaseous fission product capture during separations RT Jubin, NR Soelberg, DM Strachan, G Ilas Pacific Northwest National Lab.(PNNL), Richland, WA (United States), 2012 | 50 | 2012 |
| An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--isotopic Composition Predictions G Radulescu, IC Gauld, G Ilas, JC Wagner United States Nuclear Regulatory Commission, Office of Nuclear Regulatory …, 2012 | 48 | 2012 |
| Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE G Ilas, IC Gauld, H Liljenfeldt Nuclear Engineering and Design 273, 58-67, 2014 | 47 | 2014 |
| Validation of SCALE 5 decay heat predictions for LWR spent nuclear fuel IC Gauld, G Ilas, BD Murphy, CF Weber Nuclear Regulatory Commission report (ORNL/TM-2006/13), in preparation, 2010 | 47 | 2010 |
| Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties G Ilas, H Liljenfeldt Nuclear Engineering and Design 319, 176-184, 2017 | 43 | 2017 |
| Extended Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems BJ Ade, SM Bowman, IC Gauld, G Ilas, JS Martinez Oak Ridge National Laboratory (ORNL), 2015 | 43* | 2015 |
| Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems WBJ Marshall, BJ Ade, SM Bowman, IC Gauld, G Ilas, U Mertyurek, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 43 | 2015 |
| Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—Calvert Cliffs, Takahama, and Three Mile Island Reactors G Ilas, IC Gauld, FC Difilippo, MB Emmett Office of Nuclear Regulatory Res, 2010 | 42 | 2010 |
| A Monte Carlo based nodal diffusion model for criticality analysis of spent fuel storage lattices G Ilas, F Rahnema Annals of Nuclear Energy 30 (10), 1089-1108, 2003 | 39 | 2003 |
| Modeling and simulation of a High Flux Isotope Reactor representative core model for updated performance and safety basis assessments D Chandler, BR Betzler, EE Davidson, G Ilas Nuclear Engineering and Design 366, 110752, 2020 | 34 | 2020 |
| Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading D Chandler, B Betzler, GJ Hirtz, G Ilas, E Sunny Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2016 | 32 | 2016 |
| Uncertainties in predicted isotopic compositions for high burnup PWR spent nuclear fuel IC Gauld, G Ilas, G Radulescu US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2011 | 31 | 2011 |
| Validation of SCALE for high temperature gas-cooled reactors analysis G Ilas, D Ilas, RP Kelly, EE Sunny Oak Ridge National Laboratory (United States). Funding organisation: ORNL …, 2012 | 29 | 2012 |
| High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design BR Betzler, D Chandler, EE Davidson, G Ilas Nuclear Science and Engineering 187 (1), 81-99, 2017 | 28 | 2017 |
