Comparison of one-dimensional interface-following and enthalpy methods for the numerical solution of phase change R Griffith, B Nassersharif Numerical Heat Transfer, Part B Fundamentals 18 (2), 169-187, 1990 | 30 | 1990 |
Pedagogical implications of project selection in capstone design courses P Brackin, D Knudson, B Nassersharif, D O'bannon International Journal of Engineering Education 27 (6), 1164, 2011 | 24 | 2011 |
Assessment of technology infrastructure in Native communities LA Riley, B Nassersharif, J Mullen Economic Development Administration, US Department of Commerce, 1999 | 19 | 1999 |
Best practices in assessing capstone design projects B Nassersharif, CE Rousseau proceedings of the 2010 capstone design conference, 2010 | 18 | 2010 |
Visualization of evolution of genetic algorithms B Nassersharif, D Ence, M Au Proceedings of the World Congress on Neural Networks 1, 560-565, 1994 | 12 | 1994 |
Los Alamos PWR decay-heat-removal studies. Summary results and conclusions BE Boyack, RJ Henninger, E Horley, JF Lime, B Nassersharif, R Smith Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 1986 | 9 | 1986 |
Some best practices in industry-sponsored capstone design projects B Nassersharif, LA Riley 2012 Capstone Design Conference, 2012 | 7 | 2012 |
A stochastic cellular automata model for neutron transport MJ Gaeta, B Nassersharif Nuclear science and engineering 113 (1), 56-69, 1993 | 6 | 1993 |
Deep knowledge expert system for diagnosis of multiple-failure severe transients in nuclear power plant RP Martin, B Nassersharif Artificial Intelligence and Other Innovative Computer Applications in the …, 1988 | 6 | 1988 |
Analysis of steam-generator tube-rupture events combined with auxiliary-feedwater control-system failure for Three Mile Island-Unit 1 and Zion-Unit 1 pressurized water reactors B Nassersharif Thermal Reactor Safety Meeting, San Diego, CA, USA, 1986 | 6 | 1986 |
Rapid-response analysis of the Davis-Besse loss-of-feedwater event on June 9, 1985 JF Lime, B Nassersharif, BE Boyack Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 1986 | 6 | 1986 |
A best-estimate paradigm for diagnosis of multiple failure transients in nuclear power plants using artificial intelligence RP Martin, B Nassersharif Nuclear technology 91 (3), 297-310, 1990 | 5 | 1990 |
Dominant accident sequences in Oconee-1 pressurized water reactor JF Dearing, RJ Henninger, B Nassersharif Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 1985 | 5 | 1985 |
Alternate Steam Generator Tube Rupture Mitigation Strategies for the Three Mile Island Unit I During a Loss-of-Offsite Power B Nassersharif LA-UR-85-182, Los Alamos National Laboratory, 1985 | 4 | 1985 |
A Cellular Automata Model for Neutron Transport MJ GAETA, B NASSERSHARIF Proc. Int. Top/. Mtg. Advances in Mathematics, Computations, and Reactor Physics, 1991 | 3 | 1991 |
Intelligent automated training of back propagation neural networks B Nassersharif, V Rajan Proceedings of the AI91: Frontiers in Innovative Computing for the Nuclear …, 1991 | 3 | 1991 |
Highly vectorized algorithm for transient simulation of space reactor systems B Nassersharif, JS Peery, MD DeHart Proceedings of the 1988 ACM/IEEE conference on Supercomputing, 393-399, 1988 | 3 | 1988 |
CATALisp-an expert system for real-time diagnosis of multiple-failure transients in pressurized water reactors RP Martin, B Nassersharif Transactions of the American Nuclear Society;(USA) 56 (CONF-880601-), 1988 | 3 | 1988 |
An Advanced Highly Vectorized Heat Transfer Model B Nassersharif, MD DeHart 1988 National Heat Transfer Meeting, 1988 | 3 | 1988 |
Analysis of multiple-tube ruptures in both steam generators for the Three Mile Island-1 pressurized water reactor B Nassersharif Proceedings of third international topical meeting on reactor thermal hydraulics, 1985 | 3 | 1985 |