| 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. |
§ Research Codes
The codes behind every model.
MCNP and Serpent for Monte Carlo transport, WIMS-AECL and UWB1 for lattice and depletion checks, OpenMC since 2026. His papers compare one code against another as a matter of habit.
§1 Codes
Monte Carlo transport.
§2 Also
Lattice, depletion and computing.
- WIMS-AECL 3.1.2.1
- The Canadian industry lattice code. His MCNP6 and Serpent CANDU 6 burnup results were validated against it (PBNC 2014, thesis ch. 6).
- UWB1
- The University of West Bohemia’s fast depletion code, benchmarked on the 37-element CANDU bundle (Progress in Nuclear Energy, 2016).
- MCNPX-PoliMi
- An MCNPX variant for simulating detector responses; training workshop, University of Michigan, 2016.
- Parallel computing
- Large Monte Carlo runs on the HPCVL clusters at Queen’s University.