| Thermal effects on mass and spatial resolution during laser pulse atom probe tomography of cerium oxide R Kirchhofer, MC Teague, BP Gorman Journal of Nuclear Materials 436 (1-3), 23-28, 2013 | 60 | 2013 |
| EBSD and TEM characterization of high burn-up mixed oxide fuel M Teague, B Gorman, B Miller, J King Journal of nuclear materials 444 (1-3), 475-480, 2014 | 48 | 2014 |
| Microstructural modeling of thermal conductivity of high burn-up mixed oxide fuel M Teague, M Tonks, S Novascone, S Hayes Journal of nuclear materials 444 (1-3), 161-169, 2014 | 36 | 2014 |
| Microstructural characterization of high burn-up mixed oxide fast reactor fuel M Teague, B Gorman, J King, D Porter, S Hayes Journal of nuclear materials 441 (1-3), 267-273, 2013 | 32 | 2013 |
| Using coupled mesoscale experiments and simulations to investigate high burn-up oxide fuel thermal conductivity MC Teague, BS Fromm, MR Tonks, DP Field Jom 66, 2569-2577, 2014 | 29 | 2014 |
| Advanced fuels campaign: enhanced LWR accident tolerant fuel performance metrics S Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, ... Idaho National Laboratory Report INL/EXT, 13-29957, 2014 | 24 | 2014 |
| Reaction Processing of UltraHigh Temperature W/Ta2CBased Cermets MC Teague, GE Hilmas, WG Fahrenholtz Journal of the American Ceramic Society 92 (9), 1966-1971, 2009 | 20 | 2009 |
| Mechanical properties of reactively processed W/Ta2C-based composites MC Teague, GE Hilmas, WG Fahrenholtz Journal of the European Ceramic Society 30 (11), 2197-2201, 2010 | 19 | 2010 |
| Utilization of dual-column focused ion beam and scanning electron microscope for three dimensional characterization of high burn-up mixed oxide fuel M Teague, B Gorman Progress in Nuclear Energy 72, 67-71, 2014 | 18 | 2014 |
| Performance of low smeared density sodium-cooled fast reactor metal fuel DL Porter, HJM Chichester, PG Medvedev, SL Hayes, MC Teague Journal of Nuclear Materials 465, 464-470, 2015 | 17 | 2015 |
| Assessment of MARMOT. A Mesoscale Fuel Performance Code MR Tonks, D Schwen, Y Zhang, P Chakraborty, X Bai, B Fromm, J Yu, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015 | 17 | 2015 |
| Advanced fuels campaign light water reactor accident tolerant fuel performance metrics S Bragg-Sitton, B Merrill, M Teague, L Ott, K Rob, M Farmer, M Billone, ... INL/EXT-13-29957, 2014 | 17 | 2014 |
| Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests KE Barrett, KD Ellis, CR Glass, GA Roth, MP Teague, J Johns Nuclear Engineering and Design 294, 38-51, 2015 | 16 | 2015 |
| Gap analysis to guide doe R&D in supporting extended storage and transportation of spent nuclear fuel: An Fy2019 assessment MC Teague, SJ Saltzstein, B Hanson, KB Sorenson, GA Freeze Sandia National Lab.(SNL-NM), Albuquerque, NM (United States); Pacific …, 2019 | 15 | 2019 |
| The FIT 2.0 Model-Fuel-Cycle Integration and Tradeoffs SJ Piet, NR Soelberg, LF Pincock, EL Shaber, GM Teske Idaho National Lab.(INL), Idaho Falls, ID (United States), 2011 | 13 | 2011 |
| Engineering challenges of LWR advanced fuel cladding technology in preparation for in-reactor demonstrations KE Barrett, MP Teague, IJ Van Rooyen, SM Bragg-Sitton, KD Ellis, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2012 | 12 | 2012 |
| Advanced Fuels Campaign LWR Accident Tolerant Fuel Performance Metrics S Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, ... Idaho National Laboratory, Advanced Fuels Campaign, FCRDFUEL-2013-000264 …, 2014 | 10 | 2014 |
| Characterization and modeling of microstructural stresses in alumina MC Teague, T Rodgers, S Grutzik, S Meserole Journal of the American Ceramic Society 101 (5), 2155-2161, 2018 | 9 | 2018 |
| Enhanced LWR Accident Tolerant Fuel Performance Metrics SM Bragg-Sitton, B Merrill, M Teague, L Ott, K Robb, M Farmer, M Billone, ... INL/EXT-13-29957, Idaho National Laboratory, prepared for the US Department …, 2013 | 7 | 2013 |
| Study on the mechanism of diametral cladding strain and mixed-oxide fuel element breaching in slow-ramp extended overpower transients T Uwaba, S Maeda, T Mizuno, MC Teague Journal of nuclear materials 429 (1-3), 149-158, 2012 | 5 | 2012 |
