Postgraduate DiplomaDefense, Military Engineering & Land Systems Applications open

Diploma in Neutronic-Thermal Modelling of Advanced Fuels

Online postgraduate diploma of 800 hours in neutronic-thermal modelling of advanced fuels. 8 modules covering reactor neutronics, deterministic and Monte Carlo methods, thermal-hydraulic coupling, advanced fuels and reactors, uncertainty quantification and licensing of methods under NUREG-0800 Sections 4.3 and 4.4 and Regulatory Guide 1.203, with an assigned technical tutor.

Duration6–8 months
ModeOnline
LanguageEnglish
Start datesSet by the faculty
AwardSEIUM Institute diploma
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Learning outcomes

What you will be able to do

01

Solve neutron transport problems with deterministic and Monte Carlo methods.

02

Generate homogenised cross sections for core calculations.

03

Couple neutronic and thermal-hydraulic models.

04

Assess the behaviour of advanced fuels.

05

Analyse the characteristics of advanced reactors.

06

Quantify uncertainties and validate models.

07

Understand the licensing requirements for calculation methods.

Profile

Who it's for

  • Reactor physics engineers.
  • Nuclear safety analysts.
  • Multiphysics simulation specialists.
  • Core design engineers.
  • Advanced reactor researchers.
  • Nuclear code developers.
  • Engineering or science graduates seeking to enter nuclear engineering.
Standards & tools

What you'll work with

  • NUREG-0800 Section 4.3 (NRC standard review plan for nuclear design)
  • NUREG-0800 Section 4.4 (NRC standard review plan for thermal and hydraulic design)
  • Regulatory Guide 1.203 (transient and accident analysis methods, EMDAP)
  • ASME NQA-1 (quality assurance requirements for nuclear facilities)
  • IAEA SSG-52 (design of the reactor core for nuclear power plants)
  • ANSI/ANS-19.6.1 (reload startup physics tests for PWRs)
  • OpenMC
  • Serpent
  • MCNP
  • CASMO/SIMULATE
  • MOOSE
Syllabus

8 modules

  1. 1.1Neutron transport equation
  2. 1.2Diffusion approximation
  3. 1.3Cross sections and resonances
  4. 1.4ENDF/B-VIII.0 and JEFF-3.3 libraries
  5. 1.5Self-shielding
  6. 1.6Thermal and fast spectra
  7. 1.7Reactivity and coefficients
  8. 1.8Isotopic evolution and burnup
  9. 1.9Fission poisons
  10. 1.10Practical exercise: cell calculation with OpenMC
  1. 2.1Method of characteristics
  2. 2.2Discrete ordinates
  3. 2.3Nodal methods
  4. 2.4Continuous-energy Monte Carlo
  5. 2.5Variance reduction
  6. 2.6Serpent, OpenMC and MCNP
  7. 2.7CASMO-SIMULATE code chain
  8. 2.8Cross-section homogenisation
  9. 2.9Discontinuity factors
  10. 2.10Laboratory: Serpent versus deterministic calculation
  1. 3.1Conservation equations
  2. 3.2Subchannel models
  3. 3.3CTF code
  4. 3.4Doppler and moderator feedback
  5. 3.5Picard iteration
  6. 3.6MOOSE multiphysics framework
  7. 3.7Coupled transients
  8. 3.8Convergence criteria
  9. 3.9Validation of the coupling
  10. 3.10Workshop: simplified neutronic-thermal coupling
  1. 4.1Accident-tolerant fuels
  2. 4.2Uranium silicide
  3. 4.3Uranium nitride
  4. 4.4Doped pellets
  5. 4.5TRISO particles
  6. 4.6U-Zr metallic alloys
  7. 4.7MOX fuel
  8. 4.8HALEU uranium
  9. 4.9Thermophysical properties
  10. 4.10Case study: neutronic impact of FeCrAl cladding
  1. 5.1Small modular reactors
  2. 5.2High-temperature reactors
  3. 5.3Sodium-cooled fast reactors
  4. 5.4Lead-cooled fast reactors
  5. 5.5Molten salt reactors
  6. 5.6Microreactors
  7. 5.7Fast-spectrum neutronics
  8. 5.8Reactivity coefficients
  9. 5.9Passive safety
  10. 5.10Case study: reactivity coefficients of a high-temperature reactor
  1. 6.1OECD/NEA UAM benchmark
  2. 6.2ICSBEP and IRPhE databases
  3. 6.3Nuclear data covariance matrices
  4. 6.4Statistical sampling
  5. 6.5Sensitivity analysis
  6. 6.6VVUQ framework
  7. 6.7Critical experiments
  8. 6.8Calculation biases
  9. 6.9Validation documentation
  10. 6.10Practical exercise: uncertainty propagation by sampling
  1. 7.1NUREG-0800 Sections 4.3 and 4.4
  2. 7.2Thermal and neutronic margins
  3. 7.3Acceptance criteria
  4. 7.4Approved methodologies
  5. 7.5Software quality to NQA-1
  6. 7.6EMDAP process of RG 1.203
  7. 7.7Startup physics tests
  8. 7.8Oversight by the CSN (Spanish Nuclear Safety Council)
  9. 7.9Licensing reports
  10. 7.10Case study: analysis of thermal margins
  1. 8.1Definition of the reactor and fuel
  2. 8.2Neutronic model
  3. 8.3Thermal-hydraulic model
  4. 8.4Coupling strategy
  5. 8.5Steady-state calculation
  6. 8.6Analysis of a transient
  7. 8.7Uncertainties and sensitivities
  8. 8.8Discussion of margins
  9. 8.9Report and presentation
  10. 8.10Final project: final review with the tutor
Methodology, software & labs

How you'll learn

A 100% online programme 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 the intake, so it fits around your job.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is OpenMC, Serpent, MCNP, CASMO/SIMULATE and MOOSE, in free, academic or evaluation versions. The practical work is based on real procedures for cell and core calculations, coupled multiphysics simulation and uncertainty analysis with benchmarks. Assessment is continuous by module, plus the final project.

Standards covered: NUREG-0800 Section 4.3, NUREG-0800 Section 4.4, Regulatory Guide 1.203, ASME NQA-1, IAEA SSG-52, ANSI/ANS-19.6.1.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of NUREG-0800 Sections 4.3 and 4.4 and Regulatory Guide 1.203 applied to real cases, not as a theoretical annex.
Industry software:OpenMC, Serpent, MCNP, CASMO/SIMULATE and MOOSE, in free, academic or evaluation versions.
Final project:A coupled neutronic-thermal model of a reactor with advanced fuel, including a transient and an uncertainty analysis, reviewed by your tutor.
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.

Cell calculation
Perform a fuel cell calculation with OpenMC.
Method comparison
Compare a Serpent Monte Carlo solution with a deterministic calculation.
Coupled model
Build a simplified neutronic-thermal coupling with Doppler and moderator feedback.
Uncertainty propagation
Propagate nuclear data uncertainties by statistical sampling.
Final project
A complete coupled neutronic-thermal model of a reactor with advanced fuel, from steady state and a transient to uncertainties and margins.
Career opportunities

Where this takes you

Reactor physics engineerNuclear safety analystMultiphysics simulation specialistCore design engineerAdvanced reactor researcherNuclear code developer
Admissions & scholarships

Requirements

  • Prior technical training or professional experience in the sector. No university degree is required.
  • An internet connection and a computer able to run 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.

FAQ

Frequently asked questions

The programme totals 800 hours over 6–8 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, CASMO/SIMULATE and MOOSE, 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 final project. 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 are recognised in a higher programme in the same area (postgraduate diploma or master's). Ask about the recognition policy when you enrol.

Prior technical training or professional experience in the sector (no university degree required), a computer able to run the 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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