Course in Reactor Physics Fundamentals
300-hour online course in reactor physics fundamentals. 6 modules covering ANSI/ANS-19.6.1 (start-up physics tests after PWR refuelling outages), ANSI/ANS-8.1 (criticality safety outside reactors) and OpenMC. 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
Describe neutron interactions with matter relevant to reactors.
Explain the chain reaction and calculate the multiplication factor.
Solve the neutron diffusion equation in simple geometries.
Apply point kinetics equations to reactivity changes.
Analyse power distribution and core operation.
Use Monte Carlo codes for criticality calculations.
Perform the neutronic calculation of a simplified reactor.
Who it's for
- Reactor physics engineer who wants to specialise in Reactor Physics Fundamentals.
- Core design engineer who wants to specialise in Reactor Physics Fundamentals.
- Neutronics analyst who wants to specialise in Reactor Physics Fundamentals.
- Criticality safety engineer who wants to specialise in Reactor Physics Fundamentals.
- Power plant operations engineer who wants to specialise in Reactor Physics Fundamentals.
- Nuclear engineering researcher who wants to specialise in Reactor Physics Fundamentals.
- Engineering or science graduates seeking to enter nuclear power generation.
What you'll work with
- ANSI/ANS-19.6.1 (start-up physics tests after PWR refuelling outages)
- ANSI/ANS-8.1 (criticality safety outside reactors)
- IAEA SSG-52 (reactor core design)
- ANSI/ANS-19.3 (reaction rate and reactivity distributions)
- 10 CFR 50, Appendix A (general design criteria)
- ANSI/ANS-10.4 (verification and validation of scientific software)
- IAEA SSR-2/1 (Rev. 1) (safety of nuclear power plants: design)
6 modules · 300 h
1.1Nuclear structure and binding energy1.2Nuclear fission: mechanism and energy released1.3Fission products and their distribution1.4Prompt and delayed neutrons1.5Watt fission spectrum1.6Neutron-nucleus interactions1.7Microscopic and macroscopic cross sections1.8Resonances and Doppler effect1.9Nuclear data libraries1.10Practice: calculation of macroscopic cross sections
2.1Multiplication factor2.2Four-factor formula2.3Six-factor formula2.4Neutron leakage2.5Moderation and lethargy2.6Moderators: water, heavy water and graphite2.7Neutron thermalisation2.8Thermal utilisation factor2.9Resonance escape probability2.10Laboratory: calculation of the infinite multiplication factor (k-infinity) of a fuel cell
3.1Fick's law for neutrons3.2Single-group diffusion equation3.3Boundary conditions and extrapolation length3.4Diffusion length3.5Bare reactor: slab, cylinder and sphere3.6Geometric and material buckling3.7Reflectors and reflector savings3.8Two-group diffusion theory3.9Numerical solution by finite differences3.10Laboratory: numerical solution of the diffusion equation
4.1Point kinetics equations4.2Delayed neutron groups4.3Reactivity and units: pcm and dollars4.4Reactor period4.5Inhour equation4.6Prompt jump4.7Reactivity excursions4.8Negative temperature reactivity4.9Subcritical source and multiplication4.10Laboratory: point kinetics simulation in Python
5.1Reactivity coefficients: fuel, moderator and void5.2Xenon-135 poisoning5.3Xenon oscillations5.4Samarium-1495.5Control with rods and boron5.6Burnable poisons5.7Fuel burn-up and isotopic evolution5.8Power distribution and peaking factors5.9Decay heat5.10Case study: xenon transient after a shutdown
6.1Definition of the study reactor6.2Fuel cell calculation6.3Core criticality calculation6.4Analysis of reactivity coefficients6.5Transient simulation6.6Poisoning evaluation6.7Discussion of results6.8Project synthesis6.9Report and presentation6.10Final review with the tutor
How you'll learn
100% online training on the SEIUM campus, with downloadable material, recorded classes and assigned technical tutor. No fixed timetable: students progress at their own pace within the intake, making 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, MCNP, CASMO/SIMULATE, Python (NumPy), in free, academic or evaluation versions. Tests are studied using real procedures for criticality calculation of a fuel cell, numerical solution of the diffusion equation and point kinetics simulation. Assessment is continuous per 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.
Describe neutron interactions with matter relevant to reactors.
Explain the chain reaction and calculate the multiplication factor.
Solve the neutron diffusion equation in simple geometries.
Apply point kinetics equations to reactivity changes.
Analyse power distribution and core operation.
Where this takes you
Requirements
- No prior degree required.
- Internet connection and a computer capable of running the programme's software.
- Sufficient level of Spanish to follow reading of technical standards.
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 per week on average, compatible with a full-time job.
You will work with OpenMC, Serpent, MCNP, CASMO/SIMULATE, Python (NumPy). 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 are recognised in the higher programme. Check the recognition policy when you enrol.
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