| Advanced burner test reactor preconceptual design report. YI Chang, PJ Finck, C Grandy, J Cahalan, L Deitrich, F Dunn, D Fallin, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2008 | 200 | 2008 |
| OECD MCCI-2 Project. Final Report MT Farmer, S Lomperski, DJ Kilsdonk, RW Aeschlimann Argonne National Lab.(ANL), Argonne, IL (United States), 2010 | 92 | 2010 |
| Corium coolability under ex-vessel accident conditions for LWRs MT Farmer, DJ Kilsdonk, RW Aeschlimann Nuclear Engineering and Technology 41 (5), 575-602, 2009 | 66 | 2009 |
| Experimental evaluation of the water ingression mechanism for corium cooling S Lomperski, MT Farmer Nuclear engineering and design 237 (9), 905-917, 2007 | 61 | 2007 |
| A summary of findings from the melt coolability and concrete interaction (MCCI) program MT Farmer, S Lomperski, D Kilsdonk, RW Aeschlimann, S Basu | 56 | 2007 |
| Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction MT Farmer, L Leibowitz, KA Terrani, KR Robb Journal of nuclear materials 448 (1-3), 534-540, 2014 | 51 | 2014 |
| An advanced modular HLMC reactor concept featuring economy, safety, and proliferation resistance. BW Spencer, RN Hill, DC Wade, DJ Hill, JJ Sienicki, HS Khalil, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2000 | 51 | 2000 |
| The CORQUENCH code for modeling of ex-vessel corium coolability under top flooding conditions MT Farmer Argonne National Lab.(ANL), Argonne, IL (United States), 2018 | 45* | 2018 |
| Modeling of ex-vessel corium coolability with the CORQUENCH code MT Farmer | 44 | 2001 |
| The results of the CCI-2 reactor material experiment investigating 2-D core-concrete interaction and debris coolability MT Farmer, SW Lomperski, S Basu | 40 | 2005 |
| Revisiting insights from Three Mile Island Unit 2 postaccident examinations and evaluations in view of the Fukushima Daiichi Accident J Rempe, M Farmer, M Corradini, L Ott, R Gauntt, D Powers Nuclear Science and Engineering 172 (3), 223-248, 2012 | 36 | 2012 |
| Next generation nuclear plant methods technical program plan RR Schultz, AM Ougouag, DW Nigg, HD Gougar, RW Johnson, WK Terry, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2010 | 35 | 2010 |
| Results of reactor materials experiments investigating 2-D core-concrete interaction and debris coolability MT Farmer, S Lomperski, S Basu American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2004 | 32 | 2004 |
| Status and future direction of the melt attack and coolability experiments (MACE) program at Argonne National Laboratory. MT Farmer, BW Spencer, JL Binder, DJ Hill Argonne National Lab., IL (US), 2001 | 32 | 2001 |
| Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction KR Robb, MW Francis, MT Farmer Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/TM-2012/455, 2013 | 29 | 2013 |
| State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability JM Bonnet, M Cranga, D Vola, C Marchetto, M Kissane, F Robledo, ... Organisation for Economic Co-Operation and Development, 2017 | 28 | 2017 |
| Ex-Vessel Core Melt Modeling Comparison between MELTSPREAD-CORQUENCH and MELCOR 2.1 KR Robb, M Farmer, MW Francis Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014 | 28 | 2014 |
| Corium crust strength measurements S Lomperski, MT Farmer Nuclear engineering and design 239 (11), 2551-2561, 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 | 28 | 2007 |
| Small Modular Fast Reactor design description. YI Chang, P LoPinto, M Konomura, J Cahalan, F Dunn, M Farmer, L Krajtl, ... Argonne National Lab., Argonne, IL (US), 2005 | 28 | 2005 |
Kevin R. RobbOak Ridge National Laboratory在 ornl.gov 的电子邮件经过验证
Kevin R. RobbOak Ridge National Laboratory在 ornl.gov 的电子邮件经过验证