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Richard R. Schultz
Richard R. Schultz
Idaho National Laboratory (emeritus); Professor of Nuclear Engineering, Texas A&M & Idaho State Univ
Verified email at srv.net - Homepage
Title
Cited by
Cited by
Year
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
1722003
RELAP5/MOD3 code manual
CD Fletcher, RR Schultz
Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1992
1421992
RELAP5/MOD3 code manual user's guidelines
CD Fletcher, RR Schultz
Idaho Falls, ID, USA: Idaho National Engineering Laboratory, 1995
891995
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
702010
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
652008
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
591998
RELAP5/MOD3 Code Manual. Volume 5, Users Guidelines
CD Fletcher, RR Schultz
Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1992
571992
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
482008
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
472003
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
441996
Next generation nuclear plant phenomena identification and ranking tables (PIRTs) volume 2: Accident and thermal fluids analysis PIRTs
SJ Ball, M Corradini, SE Fisher, R Gauntt, G Geffraye, JC Gehin, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2008
40*2008
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
372010
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
361997
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
312010
RELAP5/MOD3 code manual
SM Sloan, RR Schultz, GE Wilson
EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National …, 1994
251994
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
212009
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
192006
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
192004
RELAP5-3D code includes ATHENA features and models
RA Riemke, CB Davis, RR Schultz
International Conference on Nuclear Engineering 42436, 209-217, 2006
182006
Identification and characterization of thermal fluid phenomena associated with selected operating/accident scenarios in modular high temperature gas-cooled reactors
RR Schultz, H Gougar, P Vegendla, A Obabko, J Thomas
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2017
172017
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