CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course on Fast vs Thermal Neutrons in Nuclear Design

300 h online course on fast vs thermal neutrons in nuclear design. 6 modules covering AIEA SSR-2/1 Rev.1 (safety of nuclear power plants: design), AIEA SSG-52 (reactor core design) and Serpent 2. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesSet by the faculty
AwardSEIUM Institute certificate
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Learning outcomes

What you will be able to do

01

Explain the physics of neutron interaction according to energy.

02

Analyse moderation and the characteristics of the thermal spectrum.

03

Describe the fast spectrum and the concept of breeding.

04

Compare the implications of each spectrum for core design.

05

Evaluate reactivity coefficients and inherent safety in both cases.

06

Compare existing thermal and fast reactor technologies.

07

Develop a comparative spectral design project.

Profile

Who it's for

  • Core design engineer who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Researcher in fourth-generation reactors who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Reactor physics analyst who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Fast reactor engineer who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Consultant in advanced nuclear technologies who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Fuel cycle engineer who wants to specialise in fast vs thermal neutrons in nuclear design.
  • Graduates in engineering or science seeking to enter advanced reactor design.
Standards & tools

What you'll work with

  • AIEA SSR-2/1 Rev.1 (safety of nuclear power plants: design)
  • AIEA SSG-52 (reactor core design)
  • ASME BPVC Section III, Division 5 (high-temperature reactors)
  • RCC-MRx (design code for research and advanced reactors)
  • ANSI/ANS-8.1 (criticality safety outside reactors)
  • 10 CFR 50, Appendix A (general design criteria)
Syllabus

6 modules · 300 h

  1. 1.1Microscopic and macroscopic cross sections
  2. 1.2Energy dependence: 1/v region and resonances
  3. 1.3Fission induced by thermal and fast neutrons
  4. 1.4Eta factor and neutron yield per isotope
  5. 1.5Watt fission spectrum
  6. 1.6Elastic and inelastic scattering
  7. 1.7ENDF/B and JEFF nuclear data libraries
  8. 1.8Doppler broadening of resonances
  9. 1.9Experimental measurement of cross sections
  10. 1.10Practice: reading cross sections with JANIS
  1. 2.1Energy loss per collision and lethargy
  2. 2.2Moderating power and moderating ratio
  3. 2.3Light water, heavy water and graphite
  4. 2.4Maxwell distribution and spectral hardening
  5. 2.5Resonance escape probability
  6. 2.6Four-factor formula
  7. 2.7Moderator-to-fuel ratio and over-moderation
  8. 2.8Moderator temperature coefficient
  9. 2.9Thermalisation and chemical binding effects
  10. 2.10Workshop: calculating the k-infinity of a PWR cell
  1. 3.1Absence of moderator and metallic coolants
  2. 3.2Conversion and breeding ratios
  3. 3.3Uranium-plutonium cycle in the fast spectrum
  4. 3.4Fissions of U-238 and minor actinides
  5. 3.5Sodium void coefficient
  6. 3.6Doppler effect in fast cores
  7. 3.7Delayed neutron fraction and control
  8. 3.8Transmutation and reduction of radiotoxicity
  9. 3.9Delayed neutrons of Pu-239 compared with U-235
  10. 3.10Case study: breeding balance in an SFR
  1. 4.1Core geometry and neutron leakage
  2. 4.2Fuel enrichment and composition
  3. 4.3Control rods and absorbers by spectrum
  4. 4.4Fluence damage to cladding and structures
  5. 4.5Power density and heat extraction
  6. 4.6Burnup, refuelling cycles and reactivity
  7. 4.7Neutron poisons: boron, gadolinium and xenon
  8. 4.8Comparison of inherent safety
  9. 4.9Power distribution and peaking factors
  10. 4.10Laboratory: spectral comparison with OpenMC
  1. 5.1PWR and BWR AS Thermal Reference Designs 5.2 CANDU and Heavy-Water Reactors 5.3 Graphite-Moderated High-Temperature Reactors 5.4 Sodium-Cooled Fast Reactors: Phenix and BN-800 5.5 Lead-Cooled and Gas-Cooled Fast Reactors 5.6 Generation IV Concepts of the GIF 5.7 Molten Salts in Thermal and Fast Spectra 5.8 Spectrum Choice in SMRs 5.9 Thorium Cycles in Both Spectra 5.10 Case Study: Thermal vs Fast Decision Matrix
  1. 6.1Definition of requirements and reactor mission
  2. 6.2Selection of spectrum, fuel and coolant
  3. 6.3Neutronic model of cell and assembly
  4. 6.4Calculation of k-effective and reactivity coefficients
  5. 6.5Burnup analysis and conversion ratio
  6. 6.6Safety and sustainability assessment
  7. 6.7Comparison with a reference design
  8. 6.8Conclusions and design recommendations
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

Training 100% online 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, which makes it possible to combine the course with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is Serpent 2, OpenMC, ERANOS, DRAGON5, Python (SciPy), in free, academic or evaluation versions. Tests are studied using real procedures for comparing calculated neutron spectra, cell calculations in thermal and fast spectra, and parametric core design studies. Assessment is continuous by module, plus the final integrating project.

Accreditable laboratories(EN ISO/IEC 17025) with a rotor test rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-focused final project: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:a safety-by-design approach, with cyber-OT, DIH and compliance as its 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 requirements and reactor mission

Explain the physics of neutron interaction according to energy.

Selection of spectrum, fuel and coolant

Analyse moderation and the characteristics of the thermal spectrum.

Neutronic model of cell and assembly

Describe the fast spectrum and the concept of breeding.

Calculation of k-effective and reactivity coefficients

Compare the implications of each spectrum for core design.

Burnup analysis and conversion ratio

Evaluate reactivity coefficients and inherent safety in both cases.

Career opportunities

Where this takes you

Core design engineerResearcher in fourth-generation reactorsReactor physics analystFast reactor engineerConsultant in advanced nuclear technologiesFuel cycle engineer
Admissions & scholarships

Requirements

  • No prior degree is required.
  • Internet connection and a computer capable of running the programme's software.
  • Sufficient command of 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.

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 a week, compatible with full-time work.

You will work with Serpent 2, OpenMC, ERANOS, DRAGON5, Python (SciPy). Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

A SEIUM diploma upon passing continuous assessment and the final integrating 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 recognised towards the higher-level programme. Check the recognition policy when enrolling.

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