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. Nuclear Future Challenges and Innovaion 38th Annual CNS Conference and 42nd CNS Cna Student Conference. 2018
- Gamma Heating Estimate at the McMaster Nuclear Reactor. 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. 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