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
- 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
- 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
- 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