Introduction to Nuclear Codes Course (MCNP, SCALE)
Online 300-hour course in an introduction to nuclear codes (MCNP, SCALE). 6 modules covering ANSI/ANS-8.1 (criticality safety outside reactors), ANSI/ANS-8.24 (validation of neutron transport methods for criticality) and MCNP6. 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
Explain the fundamentals of radiation transport that nuclear codes solve.
Define geometries, materials and cells in MCNP.
Configure sources, tallies and criticality calculations in MCNP.
Use the main sequences and modules of SCALE.
Calculate isotopic inventories and source terms with ORIGEN.
Interpret results and uncertainties of calculations.
Develop a calculation project with MCNP and SCALE on a practical case.
Who it's for
- Criticality safety engineer wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Reactor physics analyst wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Shielding calculation engineer wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Radioactive inventory calculation technician wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Cask licensing engineer wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Nuclear engineering researcher wishing to specialise in Introduction to Nuclear Codes (MCNP, SCALE).
- Graduates in engineering or sciences seeking to enter nuclear power plants.
What you'll work with
- ANSI/ANS-8.1 (criticality safety outside reactors)
- ANSI/ANS-8.24 (validation of neutron transport methods for criticality)
- ANSI/ANS-10.4 (V&V of nuclear scientific programmes)
- ANSI/ANS-6.1.1 (fluence-to-dose conversion factors)
- ICRP Publication 116 (conversion coefficients for external exposure)
- ASME NQA-1, Subpart 2.7 (software quality)
6 modules · 300 h
1.1Boltzmann transport equation1.2Deterministic methods versus Monte Carlo1.3Overview of codes: MCNP, SCALE, Serpent and OpenMC1.4Distribution and licensing via RSICC1.5ENDF/B-VIII.0 nuclear data libraries1.6ACE format and processing with NJOY1.7Units, normalisation and tallies1.8Code verification and validation1.9Computing resources and parallelisation1.10Practical: installation and testing of a sample case
2.1Input file structure2.2Surfaces and cells2.3Combinatorial geometry and universes2.4Lattices and repeated structures2.5Material definition and libraries2.6Thermal treatment S(α,β)2.7Geometry visualisation2.8Common geometry errors2.9Importances and exterior cells2.10Laboratory: modelling a fuel rod in MCNP
3.1Fixed sources: SDEF3.2Criticality calculation: KCODE and KSRC3.3Tallies F1 to F83.4Multipliers and response functions3.5Statistics and the ten quality tests3.6Variance reduction: weight windows3.7Tally mesh (FMESH)3.8Flux-to-dose conversion3.9ICSBEP benchmarks3.10Laboratory: keff of the Godiva sphere
4.1SCALE system architecture4.2Fulcrum interface4.3Cross-section processing: XSProc4.4Criticality with KENO-VI and CSAS4.5Cell analysis with TRITON and NEWT4.6Depletion with ORIGEN4.7Rapid calculation with ORIGAMI4.8Shielding with MAVRIC4.9Sensitivity and uncertainty with TSUNAMI4.10Laboratory: burnup of a PWR assembly with TRITON
5.1Criticality safety5.2Shielding calculations5.3Spent fuel analysis5.4Source term and decay heat5.5Research reactor physics5.6Dosimetry and radiological protection5.7Detectors and instrument response5.8Comparison between MCNP and SCALE5.9Quality assurance in calculations5.10Practical case: criticality analysis of a container
6.1Problem definition6.2Construction of the geometric model6.3Selection of data and options6.4Execution and convergence control6.5Statistical analysis of results6.6Benchmark comparison6.7Uncertainty analysis6.8Synthesis of results6.9Report 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 MCNP6, SCALE (KENO-VI, ORIGEN, TRITON), Fulcrum (SCALE interface), MCNP Visual Editor, Python, in free, academic or evaluation versions. Work is studied through real procedures: criticality calculations for reference configurations, isotopic inventory and burnup calculations, and dose-rate calculations behind shielding. Assessment is continuous per 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.
Explain the fundamentals of radiation transport that nuclear codes solve.
Define geometries, materials and cells in MCNP.
Configure sources, tallies and criticality calculations in MCNP.
Use the main sequences and modules of SCALE.
Calculate isotopic inventories and source terms with ORIGEN.
Where this takes you
Requirements
- No previous degree 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.
You will work with MCNP6, SCALE (KENO-VI, ORIGEN, TRITON), Fulcrum (SCALE interface), MCNP Visual Editor, Python. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.
An SEIUM Institute diploma upon passing continuous assessment and the integrating project. It is the Institute's own training, not an official qualification from the Ministry.
Yes. Modules passed in a course or postgraduate diploma in the same area are credited towards the advanced programme. Check the recognition policy when you enrol.
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