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Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Neutron Physics and Core Calculation Engineering

Online master's programme of 1,900 hours in neutron physics and core calculation engineering, structured in 12 modules covering nuclear physics, diffusion and transport theory, Monte Carlo methods, lattice and core calculation, burnup, reactor kinetics, advanced reactors and criticality safety, 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 nuclear physics as applied to reactors.

02

Apply neutron diffusion and transport theory.

03

Use Monte Carlo methods in criticality calculations.

04

Perform cell, assembly and core calculations.

05

Analyse burnup and design fuel reloads.

06

Study reactor kinetics and dynamics.

07

Validate neutronic calculations against international benchmarks.

Profile

Who it's for

  • Reactor physics engineers looking to deepen their core calculation skills.
  • Core design analysts.
  • Criticality safety specialists.
  • Fuel management engineers.
  • Developers of neutronics codes.
  • Researchers working on advanced reactors.
  • Engineering or science graduates seeking to enter the nuclear energy sector.
Standards & tools

What you'll work with

  • ANSI/ANS-8.1 (nuclear criticality safety in operations with fissionable materials)
  • ANSI/ANS-19.6.1 (reload startup physics tests for PWRs)
  • IAEA SSG-52 (design of the reactor core)
  • International Handbook ICSBEP (evaluated criticality safety benchmark experiments)
  • ENDF/B-VIII.0 (evaluated nuclear data library)
  • IAEA SSR-2/1 (safety of nuclear power plants: design)
  • ANSI/ANS-5.1 (decay heat power in light water reactors)
  • OpenMC
  • Serpent
  • MCNP
  • DRAGON
  • PARCS
Syllabus

12 modules · 1900 h

  1. 1.1Nuclear structure and binding energy
  2. 1.2Nuclear reactions and conservation laws
  3. 1.3Fission: mechanism and products
  4. 1.4Prompt and delayed neutrons
  5. 1.5Watt fission spectrum
  6. 1.6Radioactive decay and decay chains
  7. 1.7Microscopic and macroscopic cross sections
  8. 1.8Resonances and Doppler broadening
  9. 1.9Nuclear data libraries
  10. 1.10Case study: energy balance of U-235 fission
  1. 2.1Elastic scattering and energy loss
  2. 2.2Lethargy and logarithmic decrement
  3. 2.3The 1/E slowing-down spectrum
  4. 2.4Moderators: light water, heavy water and graphite
  5. 2.5Thermalisation and the Maxwellian spectrum
  6. 2.6Thermal scattering law S(α,β)
  7. 2.7Resonance absorption
  8. 2.8Resonance integral
  9. 2.9Resonance escape probability
  10. 2.10Practical exercise: calculating the factors of the six-factor formula
  1. 3.1Neutron diffusion equation
  2. 3.2Boundary conditions
  3. 3.3Diffusion length
  4. 3.4Bare reactor and buckling
  5. 3.5One-group diffusion theory
  6. 3.6Two-group theory
  7. 3.7Reflectors and reflector savings
  8. 3.8Multigroup theory
  9. 3.9Limitations of diffusion theory
  10. 3.10Lab: two-group diffusion solver in Python
  1. 4.1Boltzmann equation for neutrons
  2. 4.2Integral and integro-differential formulations
  3. 4.3PN approximation
  4. 4.4SN discrete ordinates
  5. 4.5Ray effect and its mitigation
  6. 4.6Method of characteristics (MOC)
  7. 4.7Collision probabilities
  8. 4.8Scattering anisotropy
  9. 4.9Acceleration methods
  10. 4.10Practical exercise: one-dimensional SN transport problem
  1. 5.1Fundamentals of random sampling
  2. 5.2Simulation of neutron histories
  3. 5.3Flux estimators and tallies
  4. 5.4Criticality and fixed-source calculations
  5. 5.5Variance reduction techniques
  6. 5.6Source convergence
  7. 5.7The MCNP, Serpent and OpenMC codes
  8. 5.8Performance and parallelisation
  9. 5.9Validation against ICSBEP benchmarks
  10. 5.10Lab: criticality calculation with OpenMC
  1. 6.1Fuel element geometry
  2. 6.2Self-shielding and resonance calculation
  3. 6.3Homogenisation and condensation
  4. 6.4Discontinuity factors
  5. 6.5Burnable poisons
  6. 6.6Control rods
  7. 6.7The CASMO and DRAGON lattice codes
  8. 6.8Generation of core libraries
  9. 6.9Verification of cell calculations
  10. 6.10Practical exercise: assembly calculation with Serpent
  1. 7.1Nodal methods
  2. 7.2Pin-by-pin power reconstruction
  3. 7.3The SIMULATE and PARCS codes
  4. 7.4Power distribution and peaking factors
  5. 7.5Reactivity coefficients
  6. 7.6Shutdown margin
  7. 7.7Control rod calculation
  8. 7.8Coupling with thermal-hydraulics
  9. 7.9Core follow
  10. 7.10Lab: nodal model of a PWR core
  1. 8.1Bateman equations
  2. 8.2Isotopic evolution
  3. 8.3Xenon and samarium poisoning
  4. 8.4Plutonium production
  5. 8.5Coupled burnup methods
  6. 8.6Reload design
  7. 8.7Loading pattern optimisation
  8. 8.8Burnup extension
  9. 8.9Spent fuel inventory
  10. 8.10Case study: optimisation of a reload pattern
  1. 9.1Point kinetics equations
  2. 9.2Delayed neutron groups
  3. 9.3Reactor period
  4. 9.4Inhour equation and reactivity
  5. 9.5Doppler and moderator feedback
  6. 9.6Reactivity transients
  7. 9.7Spatial kinetics
  8. 9.8Xenon oscillations
  9. 9.9Stability analysis in BWRs
  10. 9.10Practical exercise: solving point kinetics in Python
  1. 10.1Sodium-cooled fast reactors
  2. 10.2High-temperature reactors
  3. 10.3Molten salt reactors
  4. 10.4Small modular reactors
  5. 10.5The thorium cycle
  6. 10.6Actinide transmutation
  7. 10.7Fast and epithermal spectra
  8. 10.8Nuclear data challenges
  9. 10.9Advanced reactor benchmarks
  10. 10.10Workshop: neutronic comparison of advanced concepts
  1. 11.1Nuclear criticality safety
  2. 11.2Criticality analysis of storage
  3. 11.3Burnup credit
  4. 11.4ANSI/ANS-8 standards
  5. 11.5Validation of criticality codes
  6. 11.6Startup physics tests
  7. 11.7Reactivity measurements
  8. 11.8Licensing of core design
  9. 11.9Uncertainties in core calculations
  10. 11.10Case study: criticality analysis of a spent fuel pool
  1. 12.1Definition of the neutronic problem
  2. 12.2Selection of methods and codes
  3. 12.3Cell or assembly modelling
  4. 12.4Core calculation
  5. 12.5Burnup or kinetics analysis
  6. 12.6Validation against benchmarks
  7. 12.7Uncertainty analysis
  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 OpenMC, Serpent, MCNP, DRAGON and PARCS, in free, academic or evaluation versions. Practical work is based on real procedures for Monte Carlo criticality calculations, assembly calculations and core libraries, and point kinetics and transient simulation. Assessment is continuous by module, plus the final Master's Thesis.

Standards covered: ANSI/ANS-8.1, ANSI/ANS-19.6.1, IAEA SSG-52 (core design), International Handbook ICSBEP, ENDF/B-VIII.0, IAEA SSR-2/1, ANSI/ANS-5.1.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of ANSI/ANS-8.1, ANSI/ANS-19.6.1 and IAEA SSG-52 applied to real cases, not as a theoretical annex.
Industry software:OpenMC, Serpent, MCNP, DRAGON and PARCS, in free, academic or evaluation versions.
Master's Thesis with defence:A complete neutronic project, from cell or assembly modelling to core calculation, benchmark 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 neutronic problem
Set out the reactor configuration, objectives and the methods and codes best suited to the analysis.
Model the cell or assembly
Build a lattice model with Serpent or DRAGON and generate homogenised cross-section libraries.
Calculate the core
Develop a nodal core model to obtain power distribution, peaking factors and reactivity coefficients.
Analyse burnup and kinetics
Evaluate isotopic evolution, reload patterns or reactivity transients using point kinetics.
Master's Thesis
Validate the results against benchmarks, quantify uncertainties and present the full study, defended before a panel.
Career opportunities

Where this takes you

Reactor physics engineerCore design analystCriticality safety specialistFuel management engineerNeutronics code developerAdvanced reactor 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 OpenMC, Serpent, MCNP, DRAGON and PARCS, 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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