selected scholarly activity
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books
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conferences
- The effect of intermittent operation on local fission rate in the McMaster nuclear reactor. Canadian Nuclear Society 31st Annual Conference of the Canadian Nuclear Society and 34th CNS Cna Student Conference 2010. 1580-1592. 2010
- Reinvigorating university-based education, research and development in nuclear engineering and technology. Conte 2007 Conference on Nuclear Training and Education. 56-57. 2007
- Instrumentation monitoring using multivariate statistical projection methods. Proceedings Annual Conference Canadian Nuclear Association. 1997
- The application of artificial intelligent techniques to accelerator operations at McMaster University. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 792-795. 1993
- THE ROLE OF AI IN THE ENGINEERING DOMAIN - A PARTNERSHIP ON THE MOVE. PROCEEDINGS OF THE 5TH UNB ARTIFICIAL INTELLIGENCE SYMPOSIUM. 321-328. 1993
- ENGINEERING PROBLEM SOLVING WITH KNOWLEDGE-BASED SYSTEMS. Proceeding of Second International Forum on Expert System and Computer Simulation in Energy Engineering. 1.1.1-1.1.6. 1992
- Engineering Problem Solving with Knowledge-Based Systems. Expert Systems and Computer Simulation in Energy Engineering: Selected Papers from the Second International Forum. 83-88. 1992
- MULTITASKING STRATEGIES IN SUPPORT OF A KNOWLEDGE-BASED OPERATOR COMPANION. APPLICATIONS OF ARTIFICIAL INTELLIGENCE IN ENGINEERING VII. 1001-1015. 1992
- Fundamental concepts of modeling. The science of simulation. Proceedings of the International Centre for Heat and Mass Transfer. 3-21. 1990
- MAPLE-MNR - PRELIMINARY THERMALHYDRAULICS STUDIES. 10TH ANNUAL CONFERENCE 1989 - CANADIAN NUCLEAR SOCIETY, PROCEEDINGS VOL 3. A14-A20. 1989
- ON ASSURING QUALITY IN THERMALHYDRAULIC SYSTEM SIMULATION.. Proceedings of the Summer Computer Simulation Conference. 407-412. 1985
- THERMAL-HYDRAULIC CODE, SOPHT, AS A DESIGN TOOL. Transactions of the American Nuclear Society. 397-399. 1976
- Improvement of the Iodine Monitoring System at MNR
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journal articles
- The reactor physics characteristics of a transuranic mixed oxide fuel in a heavy water moderated reactor. Nuclear Engineering and Design. 241:3768-3776. 2011
- Simulating control rod and fuel assembly motion using moving meshes. Annals of Nuclear Energy. 35:291-303. 2008
- Loss of Coolant Accident (LOCA) Analysis for McMaster Nuclear Reactor through Probabilistic Risk Assessment (PRA). 27th Annual Conference of the Canadian Nuclear Society and 30th Canadian Nuclear Society Nuclear Energy A World of Service to Humanity. 2006. 2006
- Performance Support System for$hbox I^125$Monitoring in the McMaster University Nuclear Reactor. IEEE Transactions on Nuclear Science. 53:2328-2334. 2006
- Hydraulic study of turbulent flow in MTR-type nuclear fuel assembly. Nuclear Engineering and Design. 236:975-984. 2006
- A MULTIGRID METHOD FOR SPATIAL NEUTRON KINETICS. Annual Canadian Nuclear Society Conference. 295-306. 2004
- Fault detection and diagnosis using statistical control charts and artificial neural networks. Advanced Engineering Informatics. 12:35-47. 1998
- A numerical flow simulation based on the rate form of the equation of state. Computers and Fluids. 22:713-724. 1993
- Extensions to the approximation functions for the fast calculation of saturated water properties. Nuclear Engineering and Design. 136:381-388. 1992
- Knowledge-base design for heat exchanger selection. Engineering Applications of Artificial Intelligence. 3:210-220. 1990
- Simple functions for the fast approximation of light water thermodynamic properties. Nuclear Engineering and Design. 113:21-34. 1989
- Nuclear Safety in Ontario: A Critical Review of Quantitative Analyses. Risk Analysis. 9:43-54. 1989
- Intelligent real‐time system management: towards an operator companion for nuclear power plants. Engineering Computations. 6:97-115. 1989
- Approximate functions for the fast calculation of light-water properties at saturation. International Journal of Multiphase Flow. 14:333-348. 1988
- Rate form of the equation of state for thermalhydraulic systems: numerical considerations. Engineering Computations. 4:332-340. 1987
- CANDU-600 Heat Transport System Flow Stability. Nuclear Technology. 75:239-260. 1986
- Computer analytics for thermalhydraulics. Engineering Computations. 3:331-338. 1986
- 1a-O-9 ドリフト・フラックス法による気泡柱のシミレーション 1985
- Space-Time Nuclear Reactor Analysis by Temporal Transformation. Nuclear Science and Engineering. 55:119-128. 1974
- Temperature sensing by neutron transmission. Nuclear Instruments and Methods. 104:217-217. 1972
- A closed-form analysis for space dependent nuclear reactor transients. Journal of Nuclear Energy. 26:461-468. 1972
- Partial-range legendre polynomial solution of the neutron-transport equation. Transport Theory and Statistical Physics. 2:347-364. 1972
- Dependence of calculated void reactivity on film-boiling representation
- Direct Energy Conversion Using Semiconductor P-N Junctions. Final Project Rep. 5421-0. 3-103.
- Effects contributing to positive coolant void reactivity in CANDU. Transactions of the American Nuclear Society. 72.
- MNRSIM: An Interactive Visual Model which Links Thermal Hydraulics, Neutron Production and other Phenomena
- New Postgraduate Programs in Nuclear Engineering to Meet the Needs of the Canadian Nuclear Industry
- Nuclear education and training in the internet age
- OPTIMUM ANGULAR SEGMENTATIONS IN NEUTRON TRANSPORT ANALYSIS
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theses