| A review of the thermophysical properties of MOX and UO2 fuels JJ Carbajo, GL Yoder, SG Popov, VK Ivanov Journal of Nuclear Materials 299 (3), 181-198, 2001 | 399 | 2001 |
| A study on the rewetting temperature JJ Carbajo Nuclear Engineering and Design 84 (1), 21-52, 1985 | 177 | 1985 |
| Thermophysical properties of MOX and UO2 fuels including the effects of irradiation SG Popov, JJ Carbajo, G Yoder ORNL 27, 4-00, 2000 | 176 | 2000 |
| Pre-conceptual design of a fluoride-salt-cooled small modular advanced high temperature reactor (SmAHTR) SR Greene, JC Gehin, DE Holcomb, JJ Carbajo, D Ilas, AT Cisneros, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2011 | 143 | 2011 |
| Study of Fukushima Daiichi nuclear power station unit 4 spent-fuel pool D Wang, IC Gauld, GL Yoder, LJ Ott, GF Flanagan, MW Francis, EL Popov, ... Nuclear technology 180 (2), 205-215, 2012 | 76 | 2012 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis NR Brown, BR Betzler, JJ Carbajo, AJ Wysocki, MS Greenwood, C Gentry, ... Annals of Nuclear Energy 103, 49-59, 2017 | 50 | 2017 |
| Review and comparison among the different models for rewetting in LWR's JJ Carbajo, AD Siegel Nuclear Engineering and Design 58 (1), 33-44, 1980 | 44 | 1980 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview AL Qualls, BR Betzler, NR Brown, JJ Carbajo, MS Greenwood, R Hale, ... Annals of Nuclear Energy 107, 144-155, 2017 | 40 | 2017 |
| A direct-contact-charged direct-contact-discharged cool storage system using gas hydrate JJ Carbajo ASHRAE Trans.;(United States) 91 (CONF-850606-), 1985 | 40 | 1985 |
| Heat transfer coefficients under LOCA conditions in containment buildings JJ Carbajo Nuclear Engineering and Design 65 (3), 369-386, 1981 | 36 | 1981 |
| Implementation of liquid salt working fluids into TRACE J Richard, D Wang, G Yoder, J Carbajo, D Williams, B Forget, C Forsberg Proceedings of ICAPP 2014, 2014 | 31 | 2014 |
| Development of a Twin-Screw D2 Extruder for the ITER Pellet Injection System SJ Meitner, LR Baylor, JJ Carbajo, SK Combs, DT Fehling, CR Foust, ... Fusion science and technology 56 (1), 52-56, 2009 | 27 | 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 |
| Issues in the Use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels JC Gehin, JJ Carbajo, RJ Ellis ORNL 223, 2004, 2004 | 26 | 2004 |
| Severe accident source term characteristics for selected Peach Bottom sequences predicted by the MELCOR Code JJ Carbajo Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1993 | 26 | 1993 |
| Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety R Schmidt, T Sofu, T Wei, J Thomas, R Wigeland, J Carbajo, H Ludewig, ... SAND2011-4145. June, 2011 | 25 | 2011 |
| Parametric study on rewetting velocities obtained with a two-dimensional heat conduction code JJ Carbajo Nuclear engineering and design 92 (1), 69-87, 1986 | 23 | 1986 |
| Sodium boiling experiments in the THORS facility PA Gnadt, JJ Carbajo, JF Dearing, AE Levin, RE MacPherson, ... Nuclear engineering and design 82 (2-3), 241-280, 1984 | 21 | 1984 |
| MELCOR sensitivity studies for a low-pressure, short-term station blackout at the Peach Bottom plant JJ Carbajo Nuclear engineering and design 152 (1-3), 287-317, 1994 | 20 | 1994 |
| Fluoride salt-cooled high-temperature demonstration reactor point design AL Qualls, NR Brown, BR Betzler, J Carbajo, RE Hale, TJ Harrison, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2016 | 17 | 2016 |
