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CourseElectromobility, Batteries & Hydrogen Enrolment open

Course in Monte Carlo Applied to Radiation Transport

Online 300-hour course in Monte Carlo applied to radiation transport. 6 modules covering JCGM 101 (propagation of distributions using Monte Carlo), ANSI/ANS-6.1.1 (fluence-to-dose conversion factors) and MCNP6. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesOctober / March
LocationEurope (Madrid)
AwardSEIUM Institute diploma
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Learning outcomes

What you will be able to do

01

Apply the probabilistic foundations of the Monte Carlo method to particle transport.

02

Describe the interaction mechanisms of photons, electrons and neutrons with matter.

03

Build geometry, material and source models in transport codes.

04

Apply variance reduction techniques to improve calculation efficiency.

05

Estimate dosimetric quantities and their statistical uncertainties.

06

Validate results against benchmarks and reference measurements.

07

Develop a complete radiation transport simulation.

Profile

Who it's for

  • Shielding calculation engineer seeking to specialise in Monte Carlo applied to radiation transport.
  • Radiophysicist seeking to specialise in Monte Carlo applied to radiation transport.
  • Radiation transport analyst seeking to specialise in Monte Carlo applied to radiation transport.
  • Medical physics researcher seeking to specialise in Monte Carlo applied to radiation transport.
  • Radiation protection engineer seeking to specialise in Monte Carlo applied to radiation transport.
  • Monte Carlo simulation developer seeking to specialise in Monte Carlo applied to radiation transport.
  • Graduates in engineering or sciences looking to enter nuclear power plants.
Standards & tools

What you'll work with

  • JCGM 101 (propagation of distributions using Monte Carlo)
  • ANSI/ANS-6.1.1 (fluence-to-dose conversion factors)
  • ICRP Publication 116 (conversion coefficients for external exposure)
  • ANSI/ANS-8.24 (validation of neutron transport methods for criticality safety)
  • ICRU Report 90 (key data for ionising radiation dosimetry)
  • ANSI/ANS-10.4 (V&V of nuclear scientific software)
Syllabus

6 modules · 300 h

  1. 1.1Random variables and distributions 1.2 pseudo-random number generators 1.3 Sampling by Investment and by Rejection 1.4 law of large numbers and central limit theorem 1.5 estimators, Variance and Figure of Merit 1.6 Relative Error and Reliability Criteria 1.7 Random Walk of Particles 1.8 Mean Free Path and Distance Sampling 1.9 Origins of the Method at Los Alamos 1.10 Practice: Monte Carlo Integrals in Python
  1. 2.1Photons: photoelectric effect, Compton scattering and pair production
  2. 2.2Neutron interactions with nuclei
  3. 2.3Electrons and condensed histories
  4. 2.4Heavy charged particles and stopping power
  5. 2.5Attenuation coefficients and the XCOM database
  6. 2.6Production of secondaries and cascades
  7. 2.7Kerma, absorbed dose and fluence
  8. 2.8ICRP 116 conversion coefficients
  9. 2.9Cut-off thresholds and low-energy physics
  10. 2.10Workshop: transmission of a gamma beam through lead
  1. 3.1MCNP: structure of the input file
  2. 3.2Geant4: object-oriented architecture
  3. 3.3PENELOPE and EGSnrc for electrons
  4. 3.4FLUKA and PHITS for high energies
  5. 3.5Defining sources and spectra
  6. 3.6Tallies and track-length estimators
  7. 3.7Visualisation and debugging of geometries
  8. 3.8Parallel execution and cluster computing
  9. 3.9Selecting the code according to the application
  10. 3.10Laboratory: source and shielding in OpenMC
  1. 4.1Implicit capture and Russian roulette
  2. 4.2Geometry splitting by importance
  3. 4.3Weight windows and their generation
  4. 4.4Exponential transform
  5. 4.5Hybrid methods: CADIS and FW-CADIS
  6. 4.6ADVANTG and importance maps
  7. 4.7Point detectors and DXTRAN
  8. 4.8Risk of bias and its validation
  9. 4.9Assessment of computational efficiency
  10. 4.10Practice: deep shielding with FW-CADIS
  1. 5.1Shielding calculations for facilities
  2. 5.2Dosimetry in external beam radiotherapy
  3. 5.3Detector response functions
  4. 5.4Activation of structural materials
  5. 5.5Brachytherapy and nuclear medicine
  6. 5.6Transport in fusion and in space
  7. 5.7Occupational dose rate maps
  8. 5.8Validation with the SINBAD database
  9. 5.9ANSI/ANS-6.4 standard for concrete shielding
  10. 5.10Case study: shielding of an accelerator bunker
  1. 6.1Definition of the radiological problem
  2. 6.2Choice of code and data
  3. 6.3Construction of geometry and source
  4. 6.4Configuration of tallies
  5. 6.5Application of variance reduction
  6. 6.6Statistical analysis of results
  7. 6.7Comparison with measurements or benchmark
  8. 6.8Conclusions and technical recommendations
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

Fully 100 % online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetables: students progress at their own pace within the intake, making it possible to combine with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is MCNP6, Geant4, FLUKA, PHITS, OpenMC, in free, academic or evaluation versions. Case studies are based on real Monte Carlo shielding calculation procedures, comparison with experimental benchmarks, and studies of variance reduction techniques. Assessment is continuous by module plus the final integrative project.

Accredited laboratories(EN ISO/IEC 17025) with a rotor bench, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented Master's Thesis:safety case, test plan, compliance dossier and operating limits.
Industry mentoring:lecturers with experience in training, , eVTOL/UAM and flight test.
Flexible format(hybrid/online), international cohorts and support from SEIUM Career Services.
Ethics and safety:safety-by-design approach, cyber-OT, DIH and compliance as core pillars.
Capstone project

Build it end to end

Your final project follows the real engineering workflow, step by step, reviewed by your tutor.

Definition of the radiological problem

Apply the probabilistic foundations of the Monte Carlo method to particle transport.

Choice of code and data

Describe the interaction mechanisms of photons, electrons and neutrons with matter.

Construction of geometry and source

Build geometry, material and source models in transport codes.

Configuration of tallies

Apply variance reduction techniques to improve calculation efficiency.

Application of variance reduction

Estimate dosimetric quantities and their statistical uncertainties.

Career opportunities

Where this takes you

Shielding calculation engineerRadiophysicistRadiation transport analystMedical physics researcherRadiation protection engineerMonte Carlo simulation developer
Admissions & scholarships

Requirements

  • No prior degree required.
  • Internet connection and a computer capable of running the programme's software.
  • Sufficient command of Spanish to follow technical regulatory reading.

Ready to start?

Send your application today. Our admissions team replies within 72 hours with your study plan and funding options.

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FAQ

Frequently asked questions

The programme comprises 300 hours in total, spread over 3 to 5 months. That is an average of 10 to 15 hours per week, compatible with a full-time job.

The course works with MCNP6, Geant4, FLUKA, PHITS, OpenMC. 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. This 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 credited towards the advanced programme. Check the credit transfer policy when you enrol.

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