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M. S. M. HusseinReactor & Radiation PhysicistRev. 2026-10-01

§ Publications

Every item, with what it showed.

13 items: 1 journal article, 9 conference papers,1 doctoral thesis, a book chapter and a master's project. Each carries a one-sentence takeaway, its links, and BibTeX. Citation counts are omitted on purpose; the papers speak for themselves.

§1 Journal

Journal articles
No.YearTitleVenue
012016The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundleM. Lovecký, R. Škoda, M. S. Hussein, J. J. Song, P. K. ChanBenchmarked the University of West Bohemia's fast depletion code UWB1 on the 37-element CANDU bundle against WIMS-AECL, Serpent and MCNP6, so burnable-absorber studies can run in seconds per depletion step instead of hours.Prog. Nucl. EnergyJournal

§2 Conference

Conference papers
No.YearTitleVenue
012018Uranium Nitride Fuels for Application in CANDU ReactorsJ. Wallenius, M. HusseinNatural uranium nitride made with nitrogen-15 in a CANDU core lengthens the average bundle residence time from 210 to 360 days compared with UO₂; coolant void worth rises by 20 % and the total power coefficient halves.PHYSOR 2018Conference · Cancún, Mexico
022015Design of a MultiSpectrum CANDU-based Reactor, MSCR, with 37-Element Fuel Bundles Using Serpent CodeM. S. Hussein, H. W. Bonin, B. J. Lewis, P. K. ChanFirst public design of the Multispectrum CANDU Reactor: an inner helium-cooled fast core inside a CANDU 6 thermal core, both with 37-element bundles, sized for criticality safety and studied across several U-235 enrichments.ICMSNSE 2015Conference · Ottawa
032015Burnable Absorbers in CANDU Fuel Bundle Depletion with UWB1 CodeM. Lovecký, R. Škoda, M. S. Hussein, J. Song, P. K. ChanShowed UWB1 is suitable for studying burnable absorbers that remove the initial reactivity transient and suppress the plutonium peak in CANDU fuel, with a large saving in depletion calculation time.ICMSNSE 2015Conference · Ottawa
042014Burnup Calculation of a CANDU6 Reactor Using the Serpent and MCNP6 CodesM. S. Hussein, H. W. Bonin, B. J. LewisValidated whole-core burnup in MCNP6 and Serpent against WIMS-AECL, the industry lattice code, with k-effective versus burnup in excellent agreement. Still cited in 2025 work on SMR spent fuel in CANDU.PBNC 2014Conference · Vancouver
052014Calculation of the Radial and Axial Flux and Power Distribution for a CANDU 6 Reactor with both the MCNP6 and Serpent CodesM. S. Hussein, H. W. Bonin, B. J. LewisBuilt full 3-D MCNP6 and Serpent models of the CANDU 6 (Gentilly-2) core with 37-element bundles and compared flux and power-density maps; Serpent matched MCNP6 and was the more efficient of the two.PBNC 2014Conference · Vancouver
062013Numerical Verification/Validation of the Theory of Coupled Reactors for Deuterium Critical Assembly, using MCNP5 and Serpent CodesM. S. Hussein, B. J. Lewis, H. W. BoninRepeated the coupled-reactor verification with both MCNP5 and Serpent and found excellent agreement, establishing Serpent as valid for multipoint coupled-core calculations. Also given as a talk.CANDU Fuel 2013Conference · Kingston, Ontario
072013Numerical Verification of the Theory of Coupled Reactors for a Deuterium Critical Assembly Using MCNP5M. S. Hussein, H. W. Bonin, B. J. LewisChecked multipoint coupled-reactor theory against MCNP5 on the two-region Deuterium Critical Assembly: multiplication factors and coupling coefficients agreed as the water levels in each core were varied.CNS Annual 2013Conference · Toronto
082011Direct Statistical Mathematical Model to Calculate the Full Energy Peak Efficiency of HPGe DetectorM. S. Hussein, et al.A direct statistical model for the full-energy-peak efficiency of a high-purity germanium detector, the method of his Alexandria MSc thesis.UOIT workshop 2011Conference · Oshawa, Ontario
092011Validation of Direct Statistical Mathematical Model to Calculate Full Energy Peak Efficiency of Different Germanium Detector SizesM. S. Hussein, et al.Tested the same efficiency model across germanium detectors of different sizes.UOIT workshop 2011Conference · Oshawa, Ontario

§3 Thesis

Thesis
No.YearTitleVenue
012017Design of a Multispectrum CANDU Reactor for Burning Actinides: An Approach of Non-Proliferation and Nuclear Fuel RecyclingMohamed Salah HusseinSix full-core MSCR models in Serpent. The best uranium model destroyed 10.7 % of fissile isotopes in 1000 days; the best plutonium model 15.3 % over 2600 days. Either core alone is subcritical, so disturbing one shuts the reactor down.PhD thesis, RMCThesis · Kingston, Ontario

§4 Chapter & report

Book chapter and project report
No.YearTitleVenue
012025Comprehensive Seismic Hazard Identification, Consequences, Risk Analysis and Mitigation for the Grand Ethiopian Renaissance Dam (GERD) Main Dam and Saddle DamM. S. HusseinSeismic hazards, their consequences, a risk analysis and mitigation measures for the main dam and saddle dam of the Grand Ethiopian Renaissance Dam.MEngM projectReport
022022Emerging Augmented Reality as a Technology Tool to Enhance Learning ChemistryM. S. HusseinAugmented reality as a tool for teaching chemistry in high school, college and university classes.Book chapterBook chapter

§5 Sources & BibTeX

Links and citations.

Cited-by entries are from OpenAlex, Crossref and the citing papers themselves.

  1. 01Comprehensive Seismic Hazard Identification, Consequences, Risk Analysis and Mitigation for the Grand Ethiopian Renaissance Dam (GERD) Main Dam and Saddle Dam (2025)

    BibTeX
    @misc{hussein2025risk,
  author = {M. S. Hussein},
  title = {Comprehensive Seismic Hazard Identification, Consequences, Risk Analysis and Mitigation for the Grand Ethiopian Renaissance Dam (GERD) Main Dam and Saddle Dam},
  howpublished = {Master of Engineering Management project, Ontario Tech University},
  year = {2025},
}

  2. 02Emerging Augmented Reality as a Technology Tool to Enhance Learning Chemistry (2022)

    Full text

    BibTeX
    @incollection{hussein2022chemistry,
  author = {M. S. Hussein},
  title = {Emerging Augmented Reality as a Technology Tool to Enhance Learning Chemistry},
  booktitle = {Technology and the Curriculum: Summer 2022 (Ontario Tech University, Pressbooks)},
  year = {2022},
}

  3. 03Uranium Nitride Fuels for Application in CANDU Reactors (2018)

    KTH DiVA

    BibTeX
    @inproceedings{hussein2018candu,
  author = {J. Wallenius and M. Hussein},
  title = {Uranium Nitride Fuels for Application in CANDU Reactors},
  booktitle = {International Conference on Physics of Reactors (PHYSOR 2018)},
  year = {2018},
  pages = {3603–3611},
  address = {Cancún, Mexico},
}

  4. 04Design of a Multispectrum CANDU Reactor for Burning Actinides: An Approach of Non-Proliferation and Nuclear Fuel Recycling (2017)

    RMC eSpace

    BibTeX
    @phdthesis{hussein2017mscr,
  author = {Mohamed Salah Hussein},
  title = {Design of a Multispectrum CANDU Reactor for Burning Actinides: An Approach of Non-Proliferation and Nuclear Fuel Recycling},
  school = {Royal Military College of Canada},
  year = {2017},
  pages = {363},
  url = {https://hdl.handle.net/11264/1321},
}

  5. 05The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle (2016)

    DOI

    Cited by: Lovecký et al., Prog. Nucl. Energy 2019; Edwards, Colton & Bromley, CNL Nuclear Review 2020; Duan et al., Ann. Nucl. Energy 2025.

    BibTeX
    @article{hussein2016candu,
  author = {M. Lovecký and R. Škoda and M. S. Hussein and J. J. Song and P. K. Chan},
  title = {The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle},
  journal = {Progress in Nuclear Energy},
  year = {2016},
  pages = {127–139},
  volume = {90},
  doi = {10.1016/j.pnucene.2016.03.010},
}

  6. 06Design of a MultiSpectrum CANDU-based Reactor, MSCR, with 37-Element Fuel Bundles Using Serpent Code (2015)

    IAEA INISCNS proceedingsResearchGate

    BibTeX
    @inproceedings{hussein2015design,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis and P. K. Chan},
  title = {Design of a MultiSpectrum CANDU-based Reactor, MSCR, with 37-Element Fuel Bundles Using Serpent Code},
  booktitle = {7th International Conference on Modelling and Simulation in Nuclear Science and Engineering},
  year = {2015},
  address = {Ottawa},
}

  7. 07Burnable Absorbers in CANDU Fuel Bundle Depletion with UWB1 Code (2015)

    IAEA INISCNS proceedings

    BibTeX
    @inproceedings{hussein2015uwb1,
  author = {M. Lovecký and R. Škoda and M. S. Hussein and J. Song and P. K. Chan},
  title = {Burnable Absorbers in CANDU Fuel Bundle Depletion with UWB1 Code},
  booktitle = {7th International Conference on Modelling and Simulation in Nuclear Science and Engineering},
  year = {2015},
  address = {Ottawa},
}

  8. 08Burnup Calculation of a CANDU6 Reactor Using the Serpent and MCNP6 Codes (2014)

    IAEA INISResearchGate

    Cited by: Mohsen et al., Nuclear Technology 2025 (doi 10.1080/00295450.2025.2553262).

    BibTeX
    @inproceedings{hussein2014burnup,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis},
  title = {Burnup Calculation of a CANDU6 Reactor Using the Serpent and MCNP6 Codes},
  booktitle = {19th Pacific Basin Nuclear Conference},
  year = {2014},
  address = {Vancouver},
}

  9. 09Calculation of the Radial and Axial Flux and Power Distribution for a CANDU 6 Reactor with both the MCNP6 and Serpent Codes (2014)

    IAEA INISResearchGate

    BibTeX
    @inproceedings{hussein2014power,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis},
  title = {Calculation of the Radial and Axial Flux and Power Distribution for a CANDU 6 Reactor with both the MCNP6 and Serpent Codes},
  booktitle = {19th Pacific Basin Nuclear Conference},
  year = {2014},
  address = {Vancouver},
}

  10. 10Numerical Verification/Validation of the Theory of Coupled Reactors for Deuterium Critical Assembly, using MCNP5 and Serpent Codes (2013)

    IAEA INISCNS proceedingsPDFResearchGate

    BibTeX
    @inproceedings{hussein2013serpent,
  author = {M. S. Hussein and B. J. Lewis and H. W. Bonin},
  title = {Numerical Verification/Validation of the Theory of Coupled Reactors for Deuterium Critical Assembly, using MCNP5 and Serpent Codes},
  booktitle = {12th International Conference on CANDU Fuel},
  year = {2013},
  address = {Kingston, Ontario},
}

  11. 11Numerical Verification of the Theory of Coupled Reactors for a Deuterium Critical Assembly Using MCNP5 (2013)

    IAEA INISCNS proceedings

    BibTeX
    @inproceedings{hussein2013mcnp5,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis},
  title = {Numerical Verification of the Theory of Coupled Reactors for a Deuterium Critical Assembly Using MCNP5},
  booktitle = {34th Annual Conference of the Canadian Nuclear Society},
  year = {2013},
  address = {Toronto},
}

  12. 12Direct Statistical Mathematical Model to Calculate the Full Energy Peak Efficiency of HPGe Detector (2011)

    BibTeX
    @inproceedings{hussein2011model,
  author = {M. S. Hussein and others},
  title = {Direct Statistical Mathematical Model to Calculate the Full Energy Peak Efficiency of HPGe Detector},
  booktitle = {2nd International Workshop on Real Time Measurement, Instrumentation and Control},
  year = {2011},
  address = {Oshawa, Ontario},
}

  13. 13Validation of Direct Statistical Mathematical Model to Calculate Full Energy Peak Efficiency of Different Germanium Detector Sizes (2011)

    BibTeX
    @inproceedings{hussein2011validation,
  author = {M. S. Hussein and others},
  title = {Validation of Direct Statistical Mathematical Model to Calculate Full Energy Peak Efficiency of Different Germanium Detector Sizes},
  booktitle = {2nd International Workshop on Real Time Measurement, Instrumentation and Control},
  year = {2011},
  address = {Oshawa, Ontario},
}