Course in Neutronic Modelling in Complex Geometries
Online 300-hour course in neutronic modelling in complex geometries. 6 modules covering ANSI/ANS-10.4 (V&V of nuclear scientific software), ANSI/ANS-8.24 (validation of neutron transport methods for criticality) and OpenMC. Assigned tutor and open enrolment.
Take the controls.
Run a real engineering trade-off from this programme. Move the sliders, watch the model react in real time and beat the challenge.
What you will be able to do
Formulate the neutron transport equation and its approximations.
Apply discrete ordinates and method of characteristics deterministic methods.
Represent complex geometries using meshes and CAD models.
Model complex geometries with Monte Carlo codes.
Verify and validate neutronic models against reference benchmarks.
Quantify uncertainties arising from nuclear data and geometry.
Develop a neutronic model of a realistic complex geometry.
Who it's for
- Neutronics engineer wishing to specialise in Neutronic Modelling in Complex Geometries.
- Reactor physics analyst wishing to specialise in Neutronic Modelling in Complex Geometries.
- Shielding calculation engineer wishing to specialise in Neutronic Modelling in Complex Geometries.
- Numerical methods developer wishing to specialise in Neutronic Modelling in Complex Geometries.
- Researcher in fusion and neutronics wishing to specialise in Neutronic Modelling in Complex Geometries.
- Verification and validation analyst wishing to specialise in Neutronic Modelling in Complex Geometries.
- Graduates in engineering or science seeking to enter reactor engineering and design.
What you'll work with
- ANSI/ANS-10.4 (V&V of nuclear scientific software)
- ANSI/ANS-8.24 (validation of neutron transport methods for criticality)
- IAEA SSG-52 (reactor core design)
- ASME V&V 20 (verification and validation in numerical simulation)
- JCGM 101 (propagation of distributions by Monte Carlo)
- ASME NQA-1, Subpart 2.7 (software quality)
6 modules · 300 h
1.1Integro-differential formulation of Boltzmann1.2Phase variables: position, energy and direction1.3Boundary and interface conditions1.4Diffusion approximation and its limits1.5Multigroup discretisation in energy1.6Eigenvalue problem and k-effective1.7External sources and subcritical systems1.8Scattering anisotropy and Legendre polynomials1.9Adjoint equation and neutron importance1.10Practical: analytical solution for an infinite slab
2.1Discrete ordinates SN and ray effect2.2Spherical harmonics PN and SPN2.3Method of characteristics (MOC)2.4Collision probabilities2.5Nodal diffusion and advanced methods2.6Homogenisation and discontinuity factors2.7Two-step lattice-core scheme2.8CMFD acceleration and convergence2.9Parallelisation in space and angle2.10Laboratory: hexagonal cell with MOC in OpenMOC
3.1Constructive solid geometry (CSG)3.2Unstructured meshes and CAD models3.3Hexagonal lattices and pebble beds3.4TRISO particles and double heterogeneity3.5Overlapping and conformal meshes3.6CAD import with DAGMC3.7Geometry errors and their detection3.8Visualisation and model verification3.9Grids, spacers and axial detail3.10Workshop: CSG model of a VVER fuel assembly
4.1Particle tracking and delta-tracking4.2MCNP, Serpent and OpenMC codes4.3Flux, reaction and power tallies4.4Fission source and Shannon entropy4.5Variance reduction with weight windows4.6Continuous-energy data and probability tables4.7Thermal scattering treatment S(α,β)4.8Generation of multigroup cross sections with Monte Carlo4.9Computational cost and GPU calculation4.10Laboratory: research reactor core in Serpent
5.1ICSBEP and IRPhE benchmarks5.2BEAVRS and C5G7 benchmarks5.3Comparison metrics between codes5.4Propagation of nuclear data uncertainties5.5Sensitivities and covariance matrices5.6Total Monte Carlo sampling5.7Biases and data adjustment5.8Documentation and model quality control5.9V&V requirements for licensing5.10Case study: deterministic versus Monte Carlo in C5G7
6.1Selection of the geometric configuration6.2Construction of the geometric model6.3Preparation of nuclear data6.4Calculation with a deterministic method6.5Reference calculation with Monte Carlo6.6Analysis of power distributions6.7Quantification of uncertainties6.8Discussion of discrepancies between methods6.9Report and presentation6.10Final review with the tutor
How you'll learn
Fully 100% online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetable: students progress at their own pace within the intake, which makes it possible to combine study with work.
Each module combines theory, guided reading of the original standard and applied exercises. The working software is OpenMC, Serpent 2, DAGMC (CAD geometry for Monte Carlo), DRAGON5, Gmsh, in free, academic or evaluation versions. Case studies are based on real procedures for modelling CAD geometries for transport, international criticality benchmarks, and deterministic versus Monte Carlo comparison. Assessment is continuous, module by module, plus the final integrative project.
Build it end to end
Your final project follows the real engineering workflow, step by step, reviewed by your tutor.
Formulate the neutron transport equation and its approximations.
Apply discrete ordinates and method of characteristics deterministic methods.
Represent complex geometries using meshes and CAD models.
Model complex geometries with Monte Carlo codes.
Verify and validate neutronic models against reference benchmarks.
Where this takes you
Requirements
- No prior degree is required.
- Internet connection and a computer capable of running the programme's software.
- Sufficient Spanish to follow technical standards documentation.
Ready to start?
Send your application today. Our admissions team replies within 72 hours with your study plan and funding options.
Frequently asked questions
The programme totals 300 hours spread over 3 to 5 months. That is an average of 10 to 15 hours per week, compatible with a full-time job.
The work is carried out with OpenMC, Serpent 2, DAGMC (CAD geometry for Monte Carlo), DRAGON5, Gmsh. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.
A SEIUM own diploma upon passing the continuous assessment and the integrative project. It is in-house training, not an official qualification from the Ministry.
Yes. Modules passed in a course or postgraduate diploma in the same area can be credited towards the advanced programme. Please check the credit transfer policy when you enrol.
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