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Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Monte Carlo and Radiation Transport Engineering

Online master's programme of 1,900 hours in Monte Carlo and radiation transport engineering, structured in 12 modules covering Monte Carlo statistics, neutron and photon transport, variance reduction, shielding, Geant4 and FLUKA, dosimetry, medical, fusion and accelerator applications, and validation, with an assigned technical tutor.

Duration1900 h
ModeOnline
LanguageEnglish
Start datesSet by the faculty
AwardSEIUM Institute diploma
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Learning outcomes

What you will be able to do

01

Understand the interaction of radiation with matter.

02

Apply the statistical foundations of the Monte Carlo method.

03

Model coupled neutron and photon transport.

04

Apply variance reduction techniques.

05

Design shielding for nuclear and medical facilities.

06

Calculate dosimetric quantities for radiation protection.

07

Validate simulations against benchmarks and measurements.

Profile

Who it's for

  • Shielding engineers.
  • Radiation transport physicists.
  • Medical physicists working with Monte Carlo dose calculation.
  • Radiation protection engineers.
  • Developers of Monte Carlo simulations.
  • Researchers in detector physics.
  • Engineering or science graduates seeking to enter the nuclear energy sector.
Standards & tools

What you'll work with

  • ICRP Publication 116 (conversion coefficients for radiological protection quantities)
  • ICRP Publication 103 (recommendations of the ICRP)
  • NCRP Report 151 (shielding design for megavoltage radiotherapy facilities)
  • Directive 2013/59/Euratom (basic safety standards for radiation protection)
  • ANSI/ANS-6.4 (nuclear analysis and design of concrete radiation shielding)
  • IAEA TRS-398 (absorbed dose determination in external beam radiotherapy)
  • ASME NQA-1 (quality assurance requirements for nuclear facilities)
  • MCNP
  • OpenMC
  • Geant4
  • FLUKA
  • EGSnrc
Syllabus

12 modules · 1900 h

  1. 1.1Types of radiation: neutrons, photons, electrons and ions
  2. 1.2Interaction of particles with matter
  3. 1.3Stopping power and range
  4. 1.4The general transport equation
  5. 1.5Deterministic versus stochastic methods
  6. 1.6Applications: shielding, dosimetry, medicine and detectors
  7. 1.7History of the Monte Carlo method
  8. 1.8The code ecosystem
  9. 1.9Interaction data
  10. 1.10Case study: code selection by application
  1. 2.1Random variables and distributions
  2. 2.2Pseudo-random number generators
  3. 2.3Inversion and rejection sampling
  4. 2.4The central limit theorem
  5. 2.5Relative error and figure of merit
  6. 2.6Statistical convergence tests
  7. 2.7Correlations and histories
  8. 2.8Collision and track-length estimators
  9. 2.9Parallel runs
  10. 2.10Lab: Monte Carlo simulation of photon attenuation in Python
  1. 3.1Particle tracking in geometry
  2. 3.2Constructive solid geometry
  3. 3.3Neutron physics in Monte Carlo
  4. 3.4Coupled neutron-photon transport
  5. 3.5Photon physics and secondary electrons
  6. 3.6Flux, current and energy deposition tallies
  7. 3.7Response functions and dose conversion
  8. 3.8Source definition
  9. 3.9MCNP input and structure
  10. 3.10Practical exercise: simple shielding model in MCNP or OpenMC
  1. 4.1The need for it in deep-penetration problems
  2. 4.2Splitting and Russian roulette
  3. 4.3Weight windows
  4. 4.4Exponential transform
  5. 4.5Source biasing
  6. 4.6CADIS and FW-CADIS methods
  7. 4.7ADVANTG weight-window generators
  8. 4.8Risks of bias
  9. 4.9Efficiency assessment
  10. 4.10Lab: weight windows with ADVANTG
  1. 5.1Shielding materials: concrete, lead, polyethylene
  2. 5.2Fast and thermal neutron shielding
  3. 5.3Capture photons and secondary shielding
  4. 5.4Streaming through penetrations and ducts
  5. 5.5Skyshine
  6. 5.6Dose factor calculations
  7. 5.7Shielding of medical facilities to NCRP 151
  8. 5.8Reactor shielding
  9. 5.9Validation against SINBAD experiments
  10. 5.10Practical exercise: shielding design for an accelerator bunker
  1. 6.1Geant4 architecture
  2. 6.2Physics lists and hadronic models
  3. 6.3Geometry and materials in Geant4
  4. 6.4Scoring and analysis
  5. 6.5FLUKA and its Flair interface
  6. 6.6Heavy-ion transport
  7. 6.7Space applications
  8. 6.8Comparison between codes
  9. 6.9Cross-validation
  10. 6.10Lab: simulation of a detector in Geant4
  1. 7.1ICRU and ICRP quantities
  2. 7.2ICRP 116 conversion coefficients
  3. 7.3ICRP 110 computational phantoms
  4. 7.4Effective and equivalent dose
  5. 7.5Internal dosimetry
  6. 7.6Occupational dose calculation
  7. 7.7Material activation
  8. 7.8Residual dose after shutdown
  9. 7.9ALARA design criteria
  10. 7.10Practical exercise: dose calculation with a voxelised phantom
  1. 8.1External photon radiotherapy
  2. 8.2Proton therapy
  3. 8.3Brachytherapy
  4. 8.4Nuclear medicine and radiopharmaceutical dosimetry
  5. 8.5Simulation of accelerator treatment heads
  6. 8.6The EGSnrc and PENELOPE codes
  7. 8.7Treatment plan verification with Monte Carlo
  8. 8.8Medical imaging: CT and PET
  9. 8.9Radiotherapy regulations
  10. 8.10Lab: simulation of a photon beam with EGSnrc
  1. 9.1Gas-filled detectors
  2. 9.2Scintillators
  3. 9.3HPGe and silicon semiconductors
  4. 9.4Detector response by Monte Carlo
  5. 9.5Efficiency and calibration
  6. 9.6Gamma spectrometry
  7. 9.7Neutron detection
  8. 9.8Spectrum simulation
  9. 9.9Simulation-measurement comparison
  10. 9.10Practical exercise: simulated efficiency of an HPGe detector
  1. 10.1Fusion neutronics
  2. 10.2TBR and nuclear heating calculation
  3. 10.3Radiation damage (DPA)
  4. 10.4Activation in fusion devices
  5. 10.5Shielding of high-energy accelerators
  6. 10.6Spallation sources
  7. 10.7Radiation in space and electronics
  8. 10.8Single-event effects
  9. 10.9CAD coupling tools
  10. 10.10Case study: from CAD model to Monte Carlo with DAGMC
  1. 11.1SINBAD and ICSBEP benchmarks
  2. 11.2Input verification
  3. 11.3Statistical and systematic uncertainty
  4. 11.4Sensitivity to nuclear data
  5. 11.5Quality assurance of calculations
  6. 11.6Documentation of calculations
  7. 11.7Independent review
  8. 11.8Regulatory requirements
  9. 11.9Common errors
  10. 11.10Workshop: independent review of a shielding calculation
  1. 12.1Definition of the transport problem
  2. 12.2Selection of code and data
  3. 12.3Construction of the geometric model
  4. 12.4Definition of sources and tallies
  5. 12.5Variance reduction
  6. 12.6Analysis of results
  7. 12.7Validation and uncertainty
  8. 12.8Conclusions
  9. 12.9Master's Thesis: written report
  10. 12.10Master's Thesis: defence before a panel
Methodology, software & labs

How you'll learn

100% online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. There are no fixed timetables: you progress at your own pace within each intake, so the programme can be combined with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is MCNP, OpenMC, Geant4, FLUKA and EGSnrc, in free, academic or evaluation versions. Practical work is based on real procedures for shielding calculations with variance reduction, detector response simulation and dosimetry with computational phantoms. Assessment is continuous by module, plus the final Master's Thesis.

Standards covered: ICRP Publication 116, ICRP Publication 103, NCRP Report 151, Directive 2013/59/Euratom, ANSI/ANS-6.4, IAEA TRS-398, ASME NQA-1.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of ICRP Publication 116, ICRP Publication 103 and NCRP Report 151 applied to real cases, not as a theoretical annex.
Industry software:MCNP, OpenMC, Geant4, FLUKA and EGSnrc, in free, academic or evaluation versions.
Master's Thesis with defence:A complete radiation transport study, from geometry and source definition to variance reduction, validation and uncertainty analysis, defended before a panel.
Flexible format:100% online, no fixed timetables, compatible with full-time work.
Capstone project

Build it end to end

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

Define the transport problem
Set out the radiation source, geometry and quantities of interest, and select the most suitable code and nuclear data.
Build the geometric model
Model the facility or device in MCNP, OpenMC or Geant4, including materials and CAD-derived geometry where needed.
Set sources and tallies
Define sources, tallies and dose conversion functions for the quantities to be calculated.
Apply variance reduction
Use weight windows or CADIS methods to obtain converged results in deep-penetration regions.
Master's Thesis
Analyse and validate the results, quantify uncertainty and present the complete study, defended before a panel.
Career opportunities

Where this takes you

Shielding engineerRadiation transport physicistMedical physicistRadiation protection engineerMonte Carlo simulation developerDetector physics researcher
Admissions & scholarships

Requirements

  • University degree in engineering, science or architecture, or equivalent demonstrable professional experience.
  • Internet connection and a computer capable of running the programme software.
  • English sufficient to read technical standards.

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 totals 1,900 hours over 12–14 months. You set your own pace within each intake, and your tutor helps you plan the workload around your job.

You work with MCNP, OpenMC, Geant4, FLUKA and EGSnrc, using free, academic or evaluation versions. Your tutor indicates the free alternative wherever one exists.

A SEIUM Institute diploma, awarded on passing the continuous assessment and the Master's Thesis. It is SEIUM's own qualification, not an official state degree; its recognition depends on the programme completed and the regulations of each country.

Yes. Modules passed in a course or postgraduate diploma in the same area are recognised in the higher programme. Ask about the recognition policy when you enrol.

A university degree in engineering, science or architecture (or equivalent professional experience), a computer able to run the programme software and English sufficient to read technical standards.

Start dates are set by SEIUM's faculty for each intake. Our admissions team will confirm the next available date when you apply.

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