Richard R. Schultz
Richard R. Schultz
Idaho National Laboratory (emeritus); Professor of Nuclear Engineering, Texas A&M & Idaho State Univ
Verified email at - Homepage
Cited by
Cited by
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
RELAP5/MOD3 code manual
CD Fletcher, RR Schultz
Nuclear Regulatory Commission, 1992
RELAP5/MOD3 code manual userĘs guidelines
CD Fletcher, RR Schultz
Idaho Falls, ID, USA: Idaho National Engineering Laboratory, 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
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
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
RELAP5/MOD3 Code Manual. Volume 5, Users Guidelines
CD Fletcher, RR Schultz
Nuclear Regulatory Commission, Washington, DC (United States). Div. of†…, 1992
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
Next generation nuclear plant methods technical program plan
RR Schultz, AM Ougouag, DW Nigg, HD Gougar, RW Johnson, WK Terry, ...
Idaho National Laboratory (INL), 2010
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
Next generation nuclear plant phenomena identification and ranking tables (PIRTs)
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 Laboratory (INL), 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
Thermal hydraulics of the very high temperature gas cooled reactor
C Oh, E Kim, R Schultz, M Patterson, D Petti
Idaho National Laboratory (INL), 2009
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series
FS D'Auria, H Glaeser, S Lee, J Miák, M Modro, RR Schultz
IAEA, 2008
Stratified flows in horizontal piping of passive emergency core cooling systems
JCP Liou, DL Parks, RR Schultz, BG Williams
The 13th international conference on nuclear engineering abstracts, 2005
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
RELAP5/MOD3 code manual
SM Sloan, RR Schultz, GE Wilson
Idaho National Engineering Lab., 1994
Validations of CFD code for density-gradient driven air ingress stratified flow
CH Oh, ES Kim
International Conference on Nuclear Engineering 49347, 201-209, 2010
RELAP5-3D code includes ATHENA features and models
RA Riemke, CB Davis, RR Schultz
International Conference on Nuclear Engineering 42436, 209-217, 2006
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