selected scholarly activity
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conferences
- Axial Flux Wire Measurements at the McMaster Nuclear Reactor. Volume 9: Student Paper Competition. V009T16A086-V009T16A086. 2018
- Flux-wire Measurements and Fuel Burn-Up Estimate Comparisons with Simulations for Core-Follow Calculations at MNR Reactor. The Nuclear Future: Challenges and Innovaion - 38th Annual CNS Conference and 42nd CNS/CNA Student Conference. 2018
- Gamma Heating Estimate at the McMaster Nuclear Reactor. The Nuclear Future: Challenges and Innovaion - 38th Annual CNS Conference and 42nd CNS/CNA Student Conference. 2018
- CORE ELEMENTS IMPROVEMENTS FOR OPTIMIZATION OF RADIOISOTOPES PRODUCTION IN AN MTR-TYPE CORE. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference. 2017
- Preliminary flux measurements at the mcmaster nuclear reactor. 37th Annual Conference of the Canadian Nuclear Society and 41st Annual CNS/CNA Student Conference. 2017
- 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
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journal articles
- CFD Simulations of a Loss of Heat Sink Experiment in the McMaster Nuclear Reactor. Energies. 17:4936. 2024
- OSCAR-4 CODE SYSTEM COMPARISON AND ANALYSIS WITH A FIRST-ORDER SEMI-EMPIRICAL METHOD FOR CORE-FOLLOW DEPLETION CALCULATION IN MNR. CNL Nuclear Review. 9:73-82. 2020
- Simulation approach and code functionality assessment using deterministic and Monte Carlo codes system for U-235 core-follow depletion calculation. Progress in Nuclear Energy. 129:103501-103501. 2020
- Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor. Annals of Nuclear Energy. 145:107590-107590. 2020
- Experimental measurement and Monte Carlo code simulation of the gamma heating at different irradiation sites in a nuclear research reactor. Nuclear Engineering and Design. 364:110690-110690. 2020
- Quantification of system uncertainties in activation experiments at nuclear research reactors. Annals of Nuclear Energy. 134:432-440. 2019
- PARET-ANL Modeling of a SPERT-IV Experiment under Different Departure from Nucleate Boiling Correlations. Nuclear Technology. 177:119-131. 2012
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other
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theses