Course on Modelling Neutron Transport in Fuel
Online 300 h course in modelling neutron transport in fuel. 6 modules covering ENDF-6 Format (evaluated nuclear data), ANSI/ANS-10.4 (V&V of nuclear scientific software) and NJOY2016. Assigned tutor and open enrolment.
Take the controls.
Run a real engineering trade-off from this field. 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 as applied to fuel.
Process and use evaluated nuclear data libraries.
Apply deterministic methods to cell and assembly calculations.
Model fuel assemblies using the Monte Carlo method.
Generate homogenised cross sections for core calculations.
Verify results against benchmarks and compare methods.
Develop an integrating project on neutron transport in a fuel assembly.
Who it's for
- Reactor physics engineer wishing to specialise in Modelling of neutron transport in fuel.
- Fuel design engineer wishing to specialise in Modelling of neutron transport in fuel.
- Nuclear data analyst wishing to specialise in Modelling of neutron transport in fuel.
- Core management engineer wishing to specialise in Modelling of neutron transport in fuel.
- Transport code developer wishing to specialise in Modelling of neutron transport in fuel.
- Neutronics researcher wishing to specialise in Modelling of neutron transport in fuel.
- Engineering or science graduates seeking to enter nuclear fuel manufacturing.
What you'll work with
- ENDF-6 Format (evaluated nuclear data)
- ANSI/ANS-10.4 (V&V of nuclear scientific software)
- ANSI/ANS-19.6.1 (start-up physics testing after refuelling)
- IAEA SSG-52 (reactor core design)
- ANSI/ANS-8.24 (validation of transport methods for criticality)
- JCGM 100 (Guide to the expression of uncertainty in measurement, GUM)
6 modules · 300 h
1.1Problem variables: space, energy, direction and time1.2Microscopic and macroscopic cross sections1.3Elastic, inelastic scattering and capture1.4Fission and emitted neutron spectrum1.5Integro-differential formulation of the equation1.6Common boundary conditions1.7Eigenvalue problem and multiplication factor1.8Fixed sources versus criticality problems1.9Quantities of interest: flux, reaction rate and power1.10Exercise: formulate the problem for a cell
2.1Evaluated libraries and their contents2.2Data processing and formats2.3Energy group structure2.4Resolved and unresolved resonances2.5Resonance self-shielding2.6Doppler broadening with temperature2.7Uncertainty of nuclear data2.8Sensitivity of the result to the library2.9Validation with reference experiments2.10Practice: compare results with two libraries
3.1Diffusion approximation and its limits3.2Discrete ordinates method3.3Spherical harmonics method3.4Collision probability method3.5Method of characteristics3.6Spatial discretisation and meshes3.7Group condensation and homogenisation3.8Two-level calculation scheme3.9Convergence and acceleration3.10Practice: solve a cell with two methods
4.1Simulation of neutron histories4.2Detailed geometry of pellet, cladding and channel4.3Modelling a complete assembly4.4Flux and fission rate estimators4.5Calculation of the multiplication factor4.6Convergence of the fission source4.7Variance reduction in reactor problems4.8Calculation of homogenised cross sections4.9Comparison with the deterministic method4.10Practice: calculate the multiplication of an assembly
5.1Power distribution calculation in the assembly5.2Power peaks and channel factors5.3Effect of control rods and poisons5.4Reactivity coefficients and their calculation5.5Shielding and activation calculations5.6Criticality safety in storage5.7Verification with reference experiments5.8Documenting a calculation report5.9Software quality requirements5.10Practice: validate a model with an experiment
6.1Choosing the system to model6.2Defining geometry and materials6.3Selecting the method and data library6.4Calculation of the multiplication factor and flux6.5Power distribution and peaks6.6Sensitivity and uncertainty analysis6.7Verification against reference6.8Design conclusions6.9Calculation report6.10Defence of the work
How you'll learn
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 it with work.
Each module combines theory, guided reading of the original standard and applied exercises. The working software is NJOY2016, CASMO5, Serpent 2, OpenMC, DRAGON5, in free, academic or evaluation versions. Tests are studied using real procedures for cell and fuel assembly calculations, processing of nuclear data libraries, and comparison of deterministic and Monte Carlo methods. Assessment is continuous, module by module, plus the final integrating 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 as applied to fuel.
Process and use evaluated nuclear data libraries.
Apply deterministic methods to cell and assembly calculations.
Model fuel assemblies using the Monte Carlo method.
Generate homogenised cross sections for core calculations.
Where this takes you
Requirements
- No prior degree required.
- Internet connection and a computer capable of running the programme's software.
- Sufficient Spanish to follow technical standards texts.
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 between 10 and 15 hours a week on average, compatible with a full-time job.
You will work with NJOY2016, CASMO5, Serpent 2, OpenMC, DRAGON5. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.
SEIUM's own diploma upon passing the continuous assessment and the integrating 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 are recognised towards the advanced programme. Check the recognition policy when you enrol.
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