| Methods of reducing vehicle aerodynamic drag V Sirenko, R Pavlovs’ ky, US Rohatgi Fluids Engineering Division Summer Meeting 44755, 97-102, 2012 | 55 | 2012 |
| Application of fractional scaling analysis (FSA) to loss of coolant accidents (LOCA): Methodology development N Zuber, US Rohatgi, W Wulff, I Catton Nuclear Engineering and Design 237 (15-17), 1593-1607, 2007 | 53 | 2007 |
| Modeling of thermal hydraulic instabilities in single heated channel loop during startup transients J Paniagua, US Rohatgi, V Prasad Nuclear engineering and design 193 (1-2), 207-226, 1999 | 40 | 1999 |
| Application of fractional scaling analysis (FSA) to loss of coolant accidents (LOCA), Part 1: Methodology development N Zuber, W Wulff, US Rohatgi, I Catton The 11th International Topical Meeting on Nuclear Reactor Thermal–Hydraulics …, 2005 | 39 | 2005 |
| Application of fractional scaling analysis (FSA) to loss of coolant accidents (LOCA) W Wulff, N Zuber, US Rohatgi, I Catton Proceedings of the International Top. Meet. On Nuclear Reactor Thermal …, 2005 | 33 | 2005 |
| Non-equilibrium one-dimensional two-phase flow in variable area channels US Rohatgi, E Reshotko In: Non-equilibrium two-phase flows; Proceedings of the Winter Annual …, 1975 | 33 | 1975 |
| System scaling for the Westinghouse AP600 pressurized water reactor and related test facilities W Wulff, US Rohatgi Analysis and Results, US Nuclear Regulatory Commission, Washington, DC …, 1998 | 32 | 1998 |
| BWR stability analysis with the BNL engineering plant analyzer W Wulff, HS Cheng, AN Mallen, US Rohatgi Nuclear Regulatory Commission, Washington, DC (United States). Div. of …, 1992 | 29 | 1992 |
| A simple model for predicting the release of a liquid-vapor mixture from a large break in a pressurized container VM Fthenakis, US Rohatgi, BD Chung Journal of loss Prevention in the Process Industries 16 (1), 61-72, 2003 | 22 | 2003 |
| Stability, DNB, and CHF in natural circulation two-phase flow US Rohatgi, RB Duffey International communications in heat and mass transfer 25 (2), 161-174, 1998 | 20 | 1998 |
| Pump model for two-phase transient flow US Rohatgi Brookhaven National Lab., 1978 | 16 | 1978 |
| Simulation of SBWR startup transient and stability HS Cheng, HJ Khan, US Rohatgi Brookhaven National Lab., 1998 | 15 | 1998 |
| Impact of the nuclear option on the environment and the economy US Rohatgi, JH Jo, JC Lee, RA Bari Nuclear technology 137 (3), 252-264, 2002 | 13 | 2002 |
| Assessment of RAMONA-3B methodology with oscillatory flow tests US Rohatgi, LY Neymotin, W Wulff Nuclear engineering and design 143 (1), 69-82, 1993 | 13 | 1993 |
| Physical interpretation of geysering phenomena and periodic boiling instability at low flows RB Duffey, US Rohatgi Brookhaven National Lab.(BNL), Upton, NY (United States), 1996 | 12 | 1996 |
| Constitutive relations in TRAC-PD2 US Rohatgi, J Jo, L Neymotin Brookhaven National Lab., 1982 | 10 | 1982 |
| CFD study of prospective 1st stage centrifugal impeller design SS Panaiotti, US Rohatgi, SF Timuchev, VA Soldatov, BN Chumachenko Fluids Engineering Division Summer Meeting 42894, 861-866, 2007 | 6 | 2007 |
| A Proliferation Resistant Hexagonal Tight Lattice Fueled Core for Increased Burnup and Reduced Fuel Storage Requirements H Takahashi, U Rohatgi, TJ Downar US DOE Nuclear Energy Research Initiative, Annual Progress Report, 2000 | 5 | 2000 |
