| No. | Page | |
|---|---|---|
| 01 | The Multispectrum CANDU ReactorHis doctoral design study: a helium-cooled fast core inside a CANDU thermal core, for burning weapons-grade uranium and plutonium. | PhD, RMC 2017 |
| 02 | Monte Carlo verification and validationSix of the seven papers he published between 2013 and 2016 check a code against another code, or against theory, before any design result is used. | |
| 03 | CANDU 6 core modellingFull three-dimensional Monte Carlo models of the Gentilly-2 CANDU 6 core, with every channel and every 37-element bundle, used to map flux, power and burnup and to validate the codes against the industry's own. | |
| 04 | Fuel depletion and burnable absorbersWith the University of West Bohemia's UWB1 team, he was part of the team that benchmarked a fast depletion code on the 37-element CANDU bundle, so burnable-absorber additives can be screened quickly. | |
| 05 | Advanced fuelsUranium nitride in CANDU, thorium for small modular reactors, and a hybrid CANDU core designed to destroy weapons-grade uranium and plutonium. | |
| 06 | Radiation detectorsBefore reactors, his research was on radiation measurement: a statistical model for the efficiency of high-purity germanium detectors, and the characteristics of CZT detectors. |
§ Research
Reactor physics, checked twice.
Thirteen years of Monte Carlo reactor modelling, most of it on the CANDU 6, and a doctoral design for a reactor that burns weapons material. Most of the reactor papers test one code against another.
§1 Topics
What he has worked on.
§2 Codes
The codes he works in.
| No. | Page | |
|---|---|---|
| 01 | MCNPHis published MCNP work, from 2013, models coupled reactor cores and a full CANDU 6 core, cross-checked against Serpent and, for burnup, against the industry code WIMS-AECL. He has also taught the code. | |
| 02 | SerpentHe verified the Serpent Monte Carlo code against MCNP and WIMS-AECL on coupled cores and a full CANDU 6 core, then used it to build all six models of the reactor in his doctoral thesis. | |
| 03 | OpenMCHe completed the OECD Nuclear Energy Agency's Introduction to OpenMC in June 2026, adding the open-source Monte Carlo code to a decade of reactor models built and cross-checked in MCNP and Serpent. |