| Ettringite and C S H Portland cement phases for waste ion immobilization: A review MLD Gougar, BE Scheetz, DM Roy Waste management 16 (4), 295-303, 1996 | 779 | 1996 |
| Advanced fuel cycle cost basis DE Shropshire, KA Williams, WB Boore, JD Smith, BW Dixon, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2009 | 162 | 2009 |
| Removal of carbon-14 from irradiated graphite ML Dunzik-Gougar, TE Smith Journal of Nuclear Materials 451 (1-3), 328-335, 2014 | 65 | 2014 |
| Modeling the nuclear fuel cycle CA Juchau, ML Dunzik-Gougar, JJ Jacobson Nuclear technology 171 (2), 136-141, 2010 | 40 | 2010 |
| Characterization of 14C in neutron irradiated NBG-25 nuclear graphite D LaBrier, ML Dunzik-Gougar Journal of nuclear materials 448 (1-3), 113-120, 2014 | 39 | 2014 |
| Limited oxidation of irradiated graphite waste to remove surface carbon-14 TE Smith, S McCrory, ML Dunzik-Gougar Nuclear engineering and technology 45 (2), 211-218, 2013 | 37 | 2013 |
| Silver (Ag) transport mechanisms in TRISO coated particles: A critical review IJ Van Rooyen, ML Dunzik-Gougar, PM Van Rooyen Nuclear Engineering and Design 271, 180-188, 2014 | 36 | 2014 |
| Two-site equilibrium model for ion exchange between monovalent cations and zeolite-A in a molten salt MF Simpson, MLD Gougar Industrial & engineering chemistry research 42 (18), 4208-4212, 2003 | 32 | 2003 |
| Identification and location of 14C-bearing species in thermally treated neutron irradiated graphites NBG-18 and NBG-25: Pre-and post-thermal treatment D LaBrier, ML Dunzik-Gougar Journal of nuclear materials 460, 174-183, 2015 | 27 | 2015 |
| 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 |
| A novel waste form for disposal of spent-nuclear-fuel reprocessing waste: A vitrifiable cement MLD Gougar, BE Scheetz, DD Siemer Nuclear technology 125 (1), 93-103, 1999 | 12 | 1999 |
| A review of nuclear fuel cycle systems codes C Juchau, ML Dunzik-Gougar SINEMA LDRD PROJECT, 2006 | 11 | 2006 |
| Two-site equilibrium model for ion exchange between multi-valent cations and zeolite-A in a molten salt ML Dunzik-Gougar, MF Simpson, BE Scheetz Microporous and mesoporous materials 84 (1-3), 366-372, 2005 | 11 | 2005 |
| Chemical characterization and removal of C-14 from irradiated graphite-12010 J Cleaver, S McCrory, TE Smith, ML Dunzik-Gougar WM2012 Conference, 2012 | 10 | 2012 |
| Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at INEL MLD Gougar, DD Siemer, BE Scheetz MRS Online Proceedings Library (OPL) 412, 395, 1995 | 9 | 1995 |
| Advanced Fuel Cycle Cost Basis.(INL/EXT-07-12107) D Shropshire, K Williams, W Boore, J Smith, B Dixon, M Dunzik-Gougar, ... Idaho National Laboratory, 2007 | 8 | 2007 |
| On-line monitoring of actinide concentrations in molten salt electrolyte CW Johnson, ML Dunzik-Gougar, SX Li Idaho National Lab.(INL), Idaho Falls, ID (United States), 2006 | 8 | 2006 |
| Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models BW Spencer, NE Woolstenhulme, JL Schulthess, AD Fleming, LA Astle, ... Journal of Nuclear Materials 568, 153816, 2022 | 7 | 2022 |
| Chemical Characterization and Removal of Carbon-14 from Irradiated Graphite ML Dunzik-Gougar, J Cleaver, D LaBrier, S McCrory, K Nelson, TE Smith | 7 | 2016 |
| PCT leach tests of hot isostatically pressed (HIPped) zeolitic concretes DD Siemer, DM Roy, MW Grutzeck, MLD Gougar, BE Scheetz MRS Online Proceedings Library 465, 303-310, 1996 | 7 | 1996 |
