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Publications

Publications by RRT, Necsa

OSCAR-5 is both an industry support and research tool, and work related to development of various parts of the system has been widely published. Below you can find a collection of the most prominent publications and academic outputs related to the development of OSCAR.

Journal Articles
  1. Bokov, P. M., Botes, D., Prinsloo, R. H.,  and  Tomašević, D. I., "A multi-group homogeneous flux reconstruction method based on the ANOVA-HDMR decomposition", Nuclear Science and Engineering, vol. 197, no. 2, pp. 308–332, 2023. [Link]
  2. Erasmus, B., Hendriks, J. A., Hogenbirk, A., van der Marck, S. C. and Asquith, N. L., "Introduction of OSCAR-4 at the high flux reactor (Petten)", EPJ Web Conf., vol. 247, PHYSOR2020 –International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, 22nd Feb. 2021, Art. no. 10029. [Link]
  3. Schlünz, E.B., Bokov, P.M., and Van Vuuren, J.H., “Multiobjective 
    in-core nuclear fuel management optimisation by means of a hyperheuristic”,
    Swarm and Evolutionary Computation, 42 (2018), 58–76. [Link]
  4. Botes, D., Chifamba, S., and Bokov, P.M., “A study of the performance of a sparse grid cross section representation methodology as applied to MOXfuel”, Annals of Nuclear Energy, 99 (2017), 444–454. [Link]
  5. Schlünz, E.B. et al., “A unified methodology for single- and 
    multiobjective in-core fuel management optimisation based on augmented Chebyshev
    scalarisation and a harmony search algorithm”, Annals of Nuclear Energy,
    87 (2016), 659–670. [Link]
  6. Schlünz, E.B., Bokov, P.M., and Van Vuuren, J.H., “A comparative 
    study on multiobjective metaheuristics for solving constrained in-core fuel
    management optimisation problems”, Computers & Operations Research,
    75 (2016), 174–190. [Link]
  7. Alferov, V.P. et al., “Comparative validation of Monte Carlo codes 
    for the conversion of a research reactor”, Annals of Nuclear Energy,
    77 (Mar. 2015), 273–280. [Link]
  8. Rosenkrantz, A. et al., “Coupled 3D neutronics/thermal hydraulics 
    modeling of the SAFARI-1 MTR”, Annals of Nuclear Energy, 73 (Nov. 2014),
    122–130. [Link]
  9. Prinsloo, R.H., Tomaševic, D.I., and Moraal, H., “A practical 
    implementation of the higher-order transverse-integrated nodal diffusion method”,
    Annals of Nuclear Energy, 68 (June 2014). [Link]
  10. Müller, E.Z., “On the non-uniqueness of the nodal mathematical 
    adjoint”, Annals of Nuclear Energy, 64 (2014), 333–342. [Link]
  11. Botes, D. and Bokov, P.M., “Polynomial interpolation of few-group 
    neutron cross sections on sparse grids”, Annals of Nuclear Energy, 64
    (2014), 156–168. [Link]
  12. Van Heerden, F.A., “A coarse grained particle transport solver designed 
    specifically for graphics processing units”, Transport Theory and Statistical
    Physics, 41/1-2 (2012), 80–100. [Link]
  13. Bokov, P.M., “Asymptotic analysis for the variance-based global sensitivity 
    indices”, Science and Technology of Nuclear Installations, 2012 (2012),
    1–8. [Link]
  14. Adetula, B.A. and Bokov, P.M., “Computational method for global sensitivity 
    analysis of reactor neutronic parameters”, Science and Technology of
    Nuclear Installations, 2012 (2012). [Link]
  15. Moloko, L.E. and Belal, M.G. A.H., “Improved SAFARI-1 research reactor 
    irradiation position modeling in OSCAR-3 code system”, IEEE Transactions
    on Nuclear Science, 58/4 (2011), 1907–1912. [Link]
  16. Živanovic, R. and Bokov, P.M., “Cross-section parameterization 
    of the pebble bed modular reactor using the dimension-wise expansion model”,
    Annals of Nuclear Energy, 37/12 (Dec. 2010), 1763–1773. [Link]
  17. Colameco, D.V. et al., “A comparison between recent advances in cylindrical 
    nodal diffusion methods”, Journal of Engineering for Gas Turbines and
    Power, 132/3 (Nov. 2009), 032901. [Link]
  18. Prinsloo, R.H. and Tomaševic, D.I., “The analytic nodal method
    in cylindrical geometry”, Nuclear Engineering and Design, 238/11 (2008),
    HTR-2006: 3rd International Topical Meeting on High Temperature Reactor Technology,
    2898–2907. [Link]
  19. Ball, G., “Reactor calculations in aid of isotope production at SAFARI-1”, 
    Journal of Radioanalytical and Nuclear Chemistry, 257/1 (2003), 65–70.
    [Link]
  20. Stoker, C.C. and Weiss, Z.J., “Spatially dependent resonance cross 
    sections in a fuel rod”, Annals of Nuclear Energy, 23/9 (1996), 765–778.
    [Link]
  21. Weiss, Z.J. and Ball, G., “Ray-tracing in complicated geometries”, 
    Annals of Nuclear Energy, 18/8 (1991), 483–488. [Link]
  22. Müller, E.Z. and Weiss, Z.J., “Benchmarking with the multigroup 
    diffusion high-order response matrix method”, Annals of Nuclear Energy,
    18/9 (1991), 535–544. [Link]
  23. Müller, E.Z., “Improved Pressurized Water Reactor radial reflector 
    modeling in nodal analysis”, Nuclear Science and Engineering, 109/2
    (1991), 200–214. [Link]
  24. Müller, E.Z., “Environment-insensitive equivalent diffusion
     theory group constants for pressurized water reactor radial reflector regions”,
    Nuclear Science and Engineering, 103/4 (1989), 359–376. [Link]
Conference Publications
  1. Prinsloo, R. H., Khoza, S. N. P., Botes, D., Groenewald, S. A., Mostert, J. C., and
    Day, S. E., "Recent advances in OSCAR-5 neutronic to thermal-hydraulic interfaces,
    as applied to research reactor benchmark problems", in The European Research
    Reactor Conference (RRFM-2025), (Aix-en-Provence, France, 6th–10th Apr. 2025),
    ENS – European Nuclear Society, Apr. 2025, pp. 97–108.
  2. Prinsloo, R. H., Bokov, P. M., and Mudau, R., "Application of OSCAR-5 core optimization
    capabilities to SAFARI-1 core design", in The European Research Reactor
    Conference (RRFM-2024), (Warsaw, Poland, 21st–25th Apr. 2024), ENS –
    European Nuclear Society, Apr. 2024, pp. 239–249.
  3. Maraire, W. S., Prinsloo, R. H., Van Niekerk, F., Du Toit, M., and Chinaka, E.M.,
    "Impact of the inclusion of thorium in MTR fuel designs – an application to
    SAFARI-1 assessed with OSCAR-5", in Research Reactor Fuel Management Conference
    (RRFM-2024), (Warsaw, Poland, 21st–24th Apr. 2024), ENS – European
    Nuclear Society, 2024.
  4. Day, S. E., Prinsloo, R. H., and van Heerden, F. A., "Development of the MNR
    OSCAR-5 core follow and reload calculational model for operational support",
    in 2023 TRTR-IGORR Joint Research Reactor Conference (TRTR-IGORR-2023),
    (College Park, Maryland, USA, 18th–22nd Jun. 2023), TRTR, 2024.
  5. Prinsloo, R. H., Groenewald, S. A., and Tomašević, D. I., "Development of an embedded
    scheme for improved nodal diffusion solutions", in Proceedings of the
    International Conference on Mathematics and Computational Methods Applied to
    Nuclear Science and Engineering (M&C 2021), (Virtual Meeting, 3rd–7th Oct.
    2021), ANS – American Nuclear Society, Oct. 2021, pp. 1644–1653.
  6. Prinsloo, R. H., Groenewald, S. A., Jacobs, C., and Tomašević, D. I., "Demonstration 
    of an embedded diffusion scheme for modelling the BEAVRS benchmark problem",
    in Proceedings of the International Conference on Physics of Reactors 2022
    (PHYSOR 2022), (Pittsburgh, PA, USA, 15th–20thMay 2022), ANS – American
    Nuclear Society, Oct. 2021, pp. 1644–1653.
  7. Bokov, P. M., Botes, D., Prinsloo, R. H., and Tomašević, D.I., "HDMR-based flux 
    reconstruction method", in Proceedings of the International Conference on Mathematics
    and Computational Methods Applied to Nuclear Science and Engineering
    (M&C 2021), (Virtual Meeting, 3rd–7th Oct. 2021), ANS – American Nuclear
    Society, Oct. 2021, pp. 1374–1383.
  8. Khoza, S. N.,  Erlank, A.,  Bokov, P.M., Van Heerden, F.A., Prinsloo, R.H., and 
    Montwedi, O. E., "Evaluation of various uncertainty propagation approaches as
    applied to the calculation of the SAFARI-1 peak clad temperature", in Transactions
    of the European Research Reactor Conference (RRFM 2020), (12th–15th Oct.
    2020), Helsinki, Finland: European Nuclear Society, Oct. 2020, pp. 1–10.
  9. Bokov, P.M., Botes, D., and Tomaševic, D.I., “Estimation of corner flux
    in rectangular geometry”, International Conference on Mathematics and Computational
    Methods Applied to Nuclear Science and Engineering (M&C 2019) (Portland,
    Oregon, 2019), 2002–2012.
  10. Mudau, R., Botes, D., and Van Heerden, F.A., “Numerical modelling of control
    rod calibrations and fuel depletion at the OPAL research reactor”, The Proceedings
    of SAIP2017, the 62nd Annual Conference of the South African Institute of
    Physics, ed. J. Engelbrecht (The South African Institute of Physics (SAIP),
    31 December 2018), 344–349.
  11. Bokov, P.M., Botes, D., and Groenewald, S.A., “Table lookup of nodal equivalence
    parameters with covariance data”, PHYTRA4 - The Fourth International Conference
    on Physics and Technology of Reactors and Applications (Marrakech, Morocco:
    GMTR, Rabat, Morocco, 2018), 774–82.
  12. Prinsloo, R.H., Van Heerden, F.A.,  Botes, D., and Mudau, R., “Recent developments of the OSCAR calculational system, 
    as applied to selected examples from IAEA research reactor benchmarks”, 18th
    meeting of the International Group On Research Reactors (IGORR18) (Sydney,
    Australia, 2017), 1–15.
  13. Schlünz, E.B., Winkelman, A. J. M.,  Prinsloo, R. H., Bokov, P. M., and Van Vuuren, J. H., “In-core fuel management optimisation of the HOR reactor
    using the OSCAR-4 code system”, Transactions of the European Research Reactor
    Conference (RRFM/IGORR 2016), (Berlin: European Nuclear Society, 2016), 462–472.
  14. Moloko, L.E., Politello, J., Di Salvo, J., and D’Aletto, C., “The 2D Static Benchmark Calculations for the SAFARI-1 Research
    Reactor Core Characterisation”, Physics of Reactors 2016: Unifying Theory
    and Experiments in the 21st Century, PHYSOR 2016, American Nuclear Society
    (Sun Valley Resort, Idaho, USA, 1–5 May 2016).
  15. Schlünz, E.B., Bokov, P.M., and Van Vuuren, J.H., “On multiobjective optimisation
    approaches for in-core fuel management optimisation”, 5th Topical Meeting
    on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel
    Management V (2015), 94–104.
  16. Schlünz, E.B., Bokov, P.M., and Van Vuuren, J.H., “Application of artificial
    neural networks for predicting core parameters for the SAFARI-1 nuclear research
    reactor”, Proceedings of the 44th Annual Conference of the Operations Research
    Society of South Africa, ed. H.A. Kruger et al. (Hartbeespoort: Operations
    Research Society of South Africa, 2015), 12–22.
  17. Groenewald, S.A. and Bokov, P.M., “Propagation of uncertainty from fine-group
    cross-section data through lattice physics calculations for the SAFARI-1 research
    reactor”, in Transactions of the European Research Reactor Conference (RRFM
    2015) (Bucharest, Romania: European Nuclear Society, 19–23 April 2015), 281–290.
  18. Erasmus, B., Prinsloo, R.H., Van Heerden, F.A., Groenewald, S.A., Jacobs, C., and 
    Mashau, M., “A full core homogenization approach using serpent as
    a cross section generation tool for the OSCAR-4 code system”, Transactions
    of the European Research Reactor Conference (RRFM 2015) (Bucharest, Romania:
    European Nuclear Society, 19–23 April 2015), 667.
  19. Chifamba, S., Botes, D., Bokov, P.M., and Muronga, A.,  “Representation of the few-group homogenized cross
    sections of a MOX fuel assembly”, Proceedings of SAIP2014, the 59th Annual
    Conference of the South African Institute of Physics, ed. S. Karataglidis
    and Ch. Engelbrecht (Johannesburg: University of Johannesburg, 2015), 163–168.
  20. Schlünz, E.B., Bokov, P.M., and Van Vuuren, J.H., “Research Reactor In-Core
    Fuel Management Optimization Using the Multiobjective Cross-Entropy Method”,
    PHYSOR 2014 - The Role of Reactor Physics toward a Sustainable Future (The
    Westin Miyako Kyoto Hotel, Kyoto, Japan, September 28 – October 3, 2014),
    15.
  21. Moloko, L.E., D’Aletto, C., and Di Salvo, J., “Adaptation of ANUBIS scheme
    to SAFARI-1 core characterization”, 16h meeting of the International Group
    On Research Reactors (IGORR 16) (Bariloche, Argentina, 17–21 November 2014).
  22. Schlünz, E.B., Prinsloo, R.H., and Bokov, P.M., “In-core fuel management
    optimisation within theOSCAR-4 code system”, in European Research Reactor
    Conference (RRFM-2013) (Saint Petersburg, Russia: European Nuclear Society,
    2013), 381–390, https://euronuclear.org/meetings/rrfm2013/transactions.htm.
  23. Erasmus, B., and Van Heerden, F.A., “The Lattice Boltzmann Method applied
    to neutron transport”, International Conference on Mathematics and Computational
    Methods Applied to Nuclear Science & Engineering (M&C 2013), (Sun
    Valley, Idaho, USA: American Nuclear Society, 2013), 1335–45.
  24. Schlünz, E.B., Bokov, P.M., and Prinsloo, R.H., “Application of a harmony
    search algorithm to the core fuel reload optimisation problem for the SAFARI-1
    nuclear research reactor”, Proceedings of the 2012 ORSSA Annual Conference,
    ed. E.J. Willemse et al. (Aloe Ridge Hotel, Muldersdrift, South Africa, 2012),
    1–9.
  25. Bokov, P.M., Botes, D., and Zimin, V.G., “Pseudospectral Chebyshev Representation
    of Few-Group Cross Sections on Sparse Grids”, PHYSOR 2012 Advances in Reactor
    Physics Linking Research, Industry, and Education Knoxville, Tennessee, USA,
    April 15-20, 2012, on CD-ROM, (Knoxville, Tennessee, USA: American Nuclear
    Society, LaGrange Park, IL, 2012), 268–282.
  26. Moloko, L.E., Korochinsky, S., and Van Rooyen, T.J., “Impact of beryllium
    reflector ageing on SAFARI-1 reactor core parameters”, International Topical
    Meeting on Research Reactor Fuel Management (RRFM2011) (Rome, Italy: European
    Nuclear Society, 20–24 March 2011).
  27. Botes, D. and Bokov, P.M., “Hierarchical, Multilinear Representation of
    Few-Group Cross Sections on Sparse Grids”, in International Conference on
    Mathematics and Computational Methods Applied to Nuclear Science and Engineering
    (M&C 2011) (Rio de Janeiro: Latin American Section (LAS) / American Nuclear
    Society (ANS), 2011).
  28. Adetula, B.A. and Bokov, P.M., “Method for Calculation of Global Sensitivity
    Indices for Few-Group Cross-Section-Dependent Problems”, International Conference
    on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
    (M&C 2011) (Rio de Janeiro: Latin American Section (LAS) / American Nuclear
    Society (ANS), 2011), 1–20.
  29. Adetula, B.A. and Bokov, P.M., “Efficiency of different numerical techniques
    for evaluating global sensitivity indices when input variables are correlated
    and normally distributed”, Proceedings of SAIP2010, the 55th Annual Conference
    of the South African Institute of Physics (CSIR, Pretoria, South Africa, 2010).
  30. Tomaševic, D.I. and Müller, E.Z., “An Extension of the Multigroup Analytic
    Nodal Method (MANM) to Problems in Hexagonal-z Geometry”, International Conference
    on Mathematics, Computational Methods & Reactor Physics (M&C 2009)
    (Saratoga Springs,New York: American Nuclear Society, LaGrange Park, IL, 2009).
  31. Prinsloo, R.H. et al., “An Automated Cross Section Parameterization Method
    for MTR Application”, International Conference on Mathematics, Computational
    Methods & Reactor Physics (M&C 2009) (Saratoga Springs, New York:
    American Nuclear Society, LaGrange Park, IL, 2009).
  32. Moloko, L.E. and Belal, M.G.A.H., “Improved SAFARI-1 research reactor irradiation
    position modeling in OSCAR-3 code system”, 2009 1st International Conference
    on Advancements in Nuclear Instrumentation, Measurement Methods and their
    Applications, IEEE (June 2009), 1–7. doi:10.1109/ANIMMA.2009.5503688.
  33. Stander, G. Prinsloo, R.H., Müller, E., and Tomašević, D. I., “OSCAR-4 code system application to the SAFARI-1 reactor”,
    PHYSOR’2008 – International Conference on Reactor Physics, Nuclear Power:
    A Sustainable Resource, Interlaken, Switzerland, September 14–19, 2008 (Interlaken,
    Switzerland, 2008).
  34. Sekhri, A., D’Arcy, A., Graham, A., and Oliver, M., “Thermal-hydraulic modelling of the SAFARI-1 research
    reactor using RELAP/SCDAPSIM/MOD3.4”, PHYSOR’2008 – International Conference
    on Reactor Physics, Nuclear Power: A Sustainable Resource (Interlaken, Switzerland,
    14–19 September 2008).
  35. Bokov, P.M. et al., “A quasi-regression method for automated cross-section
    parameterization: PBMR benchmark example”, in PHYSOR’2008 - International
    Conference on Reactor Physics, Nuclear Power: A Sustainable Resource (Interlaken,
    Switzerland, 14–19 September 2008).
  36. Prinsloo, R.H. and Tomaševic, D.I., “Treatment of the central singularity
    in the conformal mapping approach to the analytic nodal method in cylindrical
    geometry”, Joint International Topical Meeting on Mathematics & Computation
    and Supercomputing in Nuclear Applications (M&C + SNA 2007) (Monterey,
    California, 15–19 April 2007), 15–19.
  37. Bokov, P.M. and Prinsloo, R.H., “Cross-Section Parameterization Using Quasi-Regression
    Approach”, Joint International Topical Meeting on Mathematics & Computation
    and Supercomputing in Nuclear Applications (M&C + SNA 2007) (Monterey,
    California, April 15–19 2007), 15–19.
  38. Prinsloo, R.H. and Tomaševic, D.I., “Development of the Analytic Nodal Method
    for Cylindrical Geometry for PBMR Application”, Proceedings of High Temperature
    Reactor 2006 Meeting (Johannesburg, South Africa, 1–4 October 2006).
  39. Müller, E.Z., Reitsma, F., and Krüger, P.P., “A Stable Nuclide Transmutation
    Procedure Free of Numerical Roundoff”, PHYSOR-2006, ANS Topical Meeting on
    Reactor Physics (Vancouver, Canada, 10–14 September 2006).
  40. Moloko, L.E., Prinsloo, R.H., and Graham A.L., “Impact on core parameters
    due to Mo-99 target plate inclusion in SAFARI-1 modelling”, Transactions of
    the 10th International Topical Meeting on Research Reactor Fuel Management,
    European Nuclear Society (ENS) in cooperation with the International Atomic
    Energy Agency (IAEA) (Kempinski Hotel Zografski, Sofia, Bulgaria: European
    Nuclear Society, 30 April – 3 May 2006), 330–334.
  41. Akdeniz, B., Müller, E., Panayotov, D., and Ivanov, K., “Consistent Neutron Kinetics Data Generation for Nodal
    Transient Calculations”, in PHYSOR-2006, ANS Topical Meeting on Reactor Physics
    (Vancouver, Canada, 10–14 September 2006).
  42. Moloko, L.E., “Improvement and validation of OSCAR-3 Usage in SAFARI-1 Nuclear
    Reactor core modelling focus on core follow calculations and Mo-99 target
    plate irradiation”, in Proceedings of SAIP2005, the 50th Annual Conference
    of the South African Institute of Physics (University of Pretoria, South Africa,
    5–7 July 2005).
  43. De Leege, P.F.A. and Reitsma, F., “HOR: Criticality Comparison Using a Nodal
    Code, Monte Carlo Codes and Plant Data”, in PHYSOR 2004 - The Physics of Fuel
    Cycles and Advanced Nuclear Systems: Global Developments (Chicago, Illinois,
    USA: American Nuclear Society, LaGrange Park, IL, 2004).
  44. Tomaševic, D.I., Joubert, W.R., and Müller, E.Z., “Asymptotic Solution of
    the Transverse Integrated Diffusion Equation in a Near-Critical Node”, in
    International Conference on Nuclear Mathematical and Computational Sciences
    (Gatlinburg, Tennessee, USA, 6–11 April 2003).
  45. Reitsma, Frederik and Müller, Erwin Z., “Flexible Exposure and Nodal Mesh
    Treatment in the 3D Nodal Simulator MGRAC: Application to a MTR Case with
    Axially Movable Assemblies”, in PHYSOR-2002, International Conference on the
    New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance
    Computing, Seoul, Korea (Seoul, Korea, 7–10 October 2002).
  46. Tomaševic, D.I., “A Higher Order Flux Reconstruction Method”, in M&C’99
    : Mathematics and Computation, Reactor Physics and Environmental Analysis
    in Nuclear Applications, ed. J.M. Aragonés, C. Ahnert, and O. Cabellos (Madrid,
    Spain: Senda Editorial, S.A., 27-30 September 1999), 782–787.
  47. Reitsma, F. and Joubert, W.R., “A calculational system to aid economical
    use of MTRs”, in International Conference on Research Reactor Fuel Management
    (RRFM’99) (Brugges, Belgium, 29–31 March 1999).
  48. Müller, Erwin Z. and Wiederhold, A.W., “Selected Non-Linear Iterative Schemes
    for the Multigroup Analytic Nodal Method”, in International Conference on
    Mathematics and Computations, Reactor Physics, and Environmental Analyses
    (Portland, Oregon, USA, 30 April – 4 May 1995).
  49. Reitsma, F. and Müller, E.Z., “Evaluation of the Use of Nodal Methods for
    MTR Neutronic Analysis”, 17th International Meeting on Reduced Enrichment
    for Research and Test Reactors (Williamsburg, Virginia, USA, 18-23 September
    1994).
  50. Muller, E.Z. et al., “Development of a core follow calculational system
    for research reactors”, 9th Pacific Basin Nuclear Conference: Nuclear Energy,
    Science and Technology – Pacific Partnership; Proceedings of the, Barton,
    A.C.T.: Institution of Engineers (Sydney, Australia, Jan. 1994), 1047–51.
  51. Vogel, D.L. and Weiss, Z.J., “A General Multigroup Formulation of the Analytic
    Nodal Method”, in International Topical Meeting on Advances in Reactor Physics
    (Charleston, South Carolina, USA, 8–11 March 1992).
  52. Joubert, W.R. and Weiss, Z.J., “A Nodal Solution of the Interface Partial
    Current Equations”, in Proceedings of the 1992 Topical Meeting on Advances
    in Reactor Physics, ii (Charleston Sheraton, Charleston, SC, USA, 8–11 March
    1992), 35–45.
  53. Weiss, Z.J. and Joubert, W.R., “Alternative Methods of Solving Response
    Matrix Equations”, in Proceedings of an International Topical Meeting on Advances
    in Mathematics, Computations and Reactor Physics (Pittsburgh, Pennsylvania,
    USA, 28 April - 2 May 1991).
Theses
  1. Jacobs, C., "Evaluation of the OSCAR-5 nodal diffusion approach to the MIT
    BEAVRS PWR experimental benchmark", MSc thesis, North-West University,
    Potchefstroom, 2021.
  2. Chinaka, E. M., "The impact of homogenized cross-section correction mechanisms
    in OSCAR-4 as applied to SAFARI-1 research reactor", MSc thesis,North-
    West University, Potchefstroom, 2019.
  3. Schlünz, E.B., “Multiobjective In-Core Fuel Management Optimisation for
    Nuclear Research Reactors”, PhD thesis (Faculty of Science at Stellenbosch
    University, Dec. 2016).
  4. Mashau, M.,  "Simulation of a selected subset of the recently published IAEA
    reactor experimental benchmark set in aid of verification and validation of the
    OSCAR-4 code system", Masters of Philosophy in Energy Studies, University
    of Johannesburg, 2016.
  5. Chifamba, S., “A Study of the Performance of a Sparse Grid Cross Section
    Representation Methodology as Applied to MOX Fuel”, MA thesis (University
    of Johannesburg, 2014).
  6. Prinsloo, R.H., “A Practical Implementation of the Higher-Order Transverse
    Integrated Nodal Diffusion Method”, PhD thesis (North-West University, Potchefstroom,
    2012).
  7. Erasmus, B., “The Lattice Boltzmann Method Applied to Linear Particle Transport”,
    MSc thesis (Potchefstroom, South Africa: North-West University, 2012).
  8. Botes, D., “Few-group Cross Section Representation Based on Sparse Grid
    Methods”, MSc thesis (Potchefstroom, South Africa: North-West University,
    2012).
  9. Moloko, L.E., “Impact of Beryllium Reflector Ageing on SAFARI-1 Reactor
    Core Parameters”, MSc thesis (North-West University, Potchefstroom, 2011).
  10. Adetula, B.A., “Global Sensitivity Analysis of Reactor Parameters”, MSc
    Thesis (North-West University, Potchefstroom, 2011).
  11. Moloko, L.E., “Improvement and Validation of OSCAR-3 Usage in SAFARI-1 Core
    Modelling”, MSc thesis (North-West University, Potchefstroom, 2007).
  12. Krüger, P.P., “Numerical Methods to Solve the Fuel Depletion Equations for
    a Nuclear Reactor”, MSc thesis (Potchestroom, South Africa: Faculty of Natural
    Sciences, Potchestroom University for CHE, 2004)
  13. Van Graan, H., “Parameterization of Few-Group Cross Sections for Reactor
    Diffusion Calculations”, Magister Scientiae thesis (Potchestroom, South Africa:
    Faculty of Natural Sciences, Potchestroom University for CHE, 1995).
  14. Vogel, D.L., “The Transverse Leakage Iterative Solution of the Multigroup
    Analytic Nodal Reactor Equations”, PhD thesis (Johannesburg, South Africa:
    Faculty of Science, University of the Witwatersrand, 1992)
  15. Joubert, W.R., “Efficient Solution of Interface Partial Current Equations
    by Rigorous Conversion to Nodal Formulation”, PhD thesis (Potchefstroom, South
    Africa: Faculty of Natural Sciences, Potchefstroom University for CHE, 1992).
  16. Müller, E.Z., “Development of an Environment-Insensitive PWR Radial Reflector
    Model Applicable to Modern Nodal Reactor Analysis Methods”, PhD thesis (Potchefstroom,
    South Africa: Faculty of Natural Sciences, Potchefstroom University for CHE,
    1989).