| NGNP preliminary Point Design–Results of the initial neutronics and thermal-hydraulic assessments PE MacDonald, JW Sterbentz, RL Sant, PD Bayless, RR Schultz, ... Idaho National Laboratory, INEEL/EXT-03-00870 Rev 1, 2003 | 174 | 2003 |
| RELAP5/MOD3 code manual CD Fletcher, RR Schultz Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1992 | 152 | 1992 |
| RELAP5/MOD3 code manual user's guidelines CD Fletcher, RR Schultz Idaho Falls, ID, USA: Idaho National Engineering Laboratory, 1995 | 94 | 1995 |
| Computational fluid dynamic analysis of core bypass flow phenomena in a prismatic VHTR H Sato, R Johnson, R Schultz Annals of Nuclear Energy 37 (9), 1172-1185, 2010 | 71 | 2010 |
| Next generation nuclear plant phenomena identification and ranking tables (PIRTs) HCG PIRT | 66* | 2008 |
| Analysis of the hot gas flow in the outlet plenum of the very high temperature reactor using coupled RELAP5-3D system code and a CFD code N Anderson, Y Hassan, R Schultz Nuclear Engineering and Design 238 (1), 274-279, 2008 | 65 | 2008 |
| Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments T Yonomoto, Y Kukita, RR Schultz Nuclear Technology 124 (1), 18-30, 1998 | 61 | 1998 |
| RELAP5/MOD3 Code Manual. Volume 5, Users Guidelines CD Fletcher, RR Schultz Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1992 | 57 | 1992 |
| Best estimate safety analysis for nuclear power plants: uncertainty evaluation F D’Auria, H Glaeser, S Lee, J Mišák, M Modro, R Schultz IAEA Safety Report Series 52, 2008 | 49 | 2008 |
| NGNP Point Design–Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03 PE MacDonald, JW Sterbentz, RL Sant, PD Bayless, RR Schultz, ... Idaho Natural Engineering and Environmental Laboratory, INEEL/EXT-03-00870 Rev 1, 2003 | 49 | 2003 |
| ROSA/AP600 testing: facility modifications and initial test results Y Kukita, T Yonomoto, H Asaka, H Nakamura, H Kumamaru, Y Anoda, ... Journal of nuclear science and technology 33 (3), 259-265, 1996 | 45 | 1996 |
| 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 | 37 | 2010 |
| Core makeup tank behavior observed during the ROSA-AP600 experiments T Yonomoto, M Kondo, Y Kukita, LS Ghan, RR Schultz Nuclear technology 119 (2), 112-122, 1997 | 37 | 1997 |
| Studies related to the Oregon State University high temperature test facility: scaling, the validation matrix, and similarities to the modular high temperature gas-cooled reactor RR Schultz, PD Bayless, RW Johnson, WT Taitano, JR Wolf, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2010 | 31 | 2010 |
| RELAP5-3D code manual. Volume V: User’s guidelines RR Schultz INEEL-EXT-98-00084. Rev. 2.2, October, 2003 | 25 | 2003 |
| RELAP5/MOD3 code manual SM Sloan, RR Schultz, GE Wilson EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National …, 1994 | 25 | 1994 |
| Thermal hydraulics of the very high temperature gas cooled reactor C Oh, E Kim, R Schultz, M Patterson, D Petti Idaho National Lab.(INL), Idaho Falls, ID (United States), 2009 | 21 | 2009 |
| RELAP5-3D code includes ATHENA features and models RA Riemke, CB Davis, RR Schultz International Conference on Nuclear Engineering 42436, 209-217, 2006 | 20 | 2006 |
| Next generation nuclear plant-design methods development and validation research and development program plan RR Schultz, DW Nigg, AM Ougouag, WK Terry, JR Wolf, HD Gougar, ... Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho, 2004 | 20 | 2004 |
| Investigation of fundamental thermal-hydraulic phenomena in advanced gas-cooled reactors DM McEligot, GE McCreery, RR Schultz, J Lee, P Hejzlar, P Stahle, ... INL/EXT-06-11801, MIT-GFR-042, 2006 | 19 | 2006 |
