| Assessment of candidate molten salt coolants for the advanced high temperature reactor (AHTR) DF Williams Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2006 | 562 | 2006 |
| Denovo: A new three-dimensional parallel discrete ordinates code in SCALE TM Evans, AS Stafford, RN Slaybaugh, KT Clarno Nuclear technology 171 (2), 171-200, 2010 | 389 | 2010 |
| The virtual environment for reactor applications (VERA): design and architecture JA Turner, K Clarno, M Sieger, R Bartlett, B Collins, R Pawlowski, ... Journal of Computational Physics 326, 544-568, 2016 | 198 | 2016 |
| VERA core simulator methodology for pressurized water reactor cycle depletion B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ... Nuclear Science and Engineering 185 (1), 217-231, 2017 | 120 | 2017 |
| Evaluation of salt coolants for reactor applications DF Williams, KT Clarno Nuclear technology 163 (3), 330-343, 2008 | 70 | 2008 |
| Trade Studies on the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report DT Ingersoll, CW Forsberg, PE MacDonald, KT Clarno ORNL/TM-2006/140, Oak Ridge National Laboratory, 2007 | 69 | 2007 |
| An assessment of coupling algorithms for nuclear reactor core physics simulations S Hamilton, M Berrill, K Clarno, R Pawlowski, A Toth, CT Kelley, T Evans, ... Journal of Computational Physics 311, 241-257, 2016 | 66 | 2016 |
| Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel MHA Piro, J Banfield, KT Clarno, S Simunovic, TM Besmann, BJ Lewis, ... Journal of Nuclear Materials 441 (1-3), 240-251, 2013 | 64 | 2013 |
| Analysis of Anderson acceleration on a simplified neutronics/thermal hydraulics system A Toth, CT Kelley, SR Slattery, SP Hamilton, KT Clarno, RPP Pawlowski Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2015 | 54 | 2015 |
| Capturing the effects of unlike neighbors in single-assembly calculations KT Clarno, ML Adams Nuclear science and engineering 149 (2), 182-196, 2005 | 53 | 2005 |
| VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12 A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ... Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016 | 52 | 2016 |
| Implementation of two-level coarse-mesh finite difference acceleration in an arbitrary geometry, two-dimensional discrete ordinates transport method Z Zhong, TJ Downar, Y Xu, MD DeHart, KT Clarno Nuclear science and engineering 158 (3), 289-298, 2008 | 44 | 2008 |
| The AMP (Advanced MultiPhysics) nuclear fuel performance code KT Clarno, B Philip, WK Cochran, RS Sampath, S Allu, P Barai, ... Nuclear Engineering and Design 252, 108-120, 2012 | 39 | 2012 |
| High fidelity modeling of pellet-clad interaction using the CASL virtual environment for reactor applications KT Clarno, RP Pawlowski, RO Montgomery, TM Evans, BS Collins, ... Mathematics and Computations, Supercomputing in Nuclear Applications and …, 2015 | 35 | 2015 |
| VERA core simulator methodology for PWR cycle depletion B Kochunas, BS Collins, D Jabaay, KS Kim, A Graham, S Stimpson, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Oak Ridge …, 2015 | 32 | 2015 |
| Coupled neutronics and thermal-hydraulic solution of a full core PWR using VERA-CS S Palmtag, K Clarno, G Davidson, R Salko, T Evans, J Turner, R Schmidt Proceedings of PHYSOR, 2014 | 32 | 2014 |
| Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 S Stimpson, J Powers, K Clarno, R Pawlowski, R Gardner, S Novascone, ... Nuclear Engineering and Design 327, 172-186, 2018 | 31 | 2018 |
| Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure KS Kim, ML Williams, D Wiarda, KT Clarno Annals of Nuclear Energy 133, 46-58, 2019 | 29 | 2019 |
| Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2008 T Primm, D Chandler, G Ilas, JH Miller, JD Sease, BC Jolly Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2009 | 28 | 2009 |
| Trade studies for the liquid-salt-cooled very high-temperature reactor: fiscal year 2006 progress report KT Clarno, CW Forsberg, JC Gehin, CO Slater, JJ Carbajo, DF Williams, ... ORNL/TM-2006 140, 35, 2007 | 26 | 2007 |
Benjamin CollinsOak Ridge National LaboratoryEmail verificata su ornl.gov
