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Fusion Neutron Generation Course

Online 300-hour course in fusion neutron generation. 6 modules covering ASTM E261 (neutron fluence determination by activation), ASTM E722 (characterisation of neutron spectra at 1 MeV equivalent fluence) and MCNP. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesSet by the faculty
AwardSEIUM Institute diploma
Enrol now View syllabus Ask an advisor
Virtual lab · try it before you enrol

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Learning outcomes

What you will be able to do

01

Explain the fusion reactions that produce neutrons and their spectra.

02

Describe fusion neutron sources and their applications.

03

Apply neutron diagnostic techniques and activation dosimetry.

04

Calculate neutron transport with Monte Carlo codes.

05

Evaluate the effects of neutrons on materials, activation and damage.

06

Interpret nuclear data from evaluated libraries.

07

Carry out a neutronics analysis of a fusion configuration.

Profile

Who it's for

  • Fusion neutronics engineer looking to specialise in fusion neutron generation.
  • Plasma diagnostics physicist looking to specialise in fusion neutron generation.
  • Neutron dosimetry specialist looking to specialise in fusion neutron generation.
  • Fusion materials researcher looking to specialise in fusion neutron generation.
  • Radiation protection technician looking to specialise in fusion neutron generation.
  • Neutron source engineer looking to specialise in fusion neutron generation.
  • Graduates in engineering or science seeking to enter fusion research.
Standards & tools

What you'll work with

  • ASTM E261 (neutron fluence determination by activation)
  • ASTM E722 (characterisation of neutron spectra at 1 MeV equivalent fluence)
  • ISO 8529-1 (reference neutron radiations)
  • ASTM E693 (neutron exposure in displacements per atom)
  • IEC 61005 (neutron ambient dose equivalent meters)
  • ASME BPVC Section III, Division 4 (fusion device components)
  • Directive 2013/59/Euratom (basic safety standards)
Syllabus

6 modules · 300 h

  1. 1.1D-T, D-D and D-He3 reactions
  2. 1.2Energy balance and kinematic sharing
  3. 1.3Cross sections and reactivity
  4. 1.4Neutron spectrum of 14.1 and 2.45 MeV
  5. 1.5Thermal broadening of the spectrum
  6. 1.6Secondary neutrons and scattering
  7. 1.7Neutron yield and fusion power
  8. 1.8Relationship between neutrons and Q gain
  9. 1.9Aneutronic fusion and its limits
  10. 1.10Practice: calculating the neutron rate of a D-T plasma
  1. 2.1Sealed-tube neutron generators
  2. 2.2Electrostatic fusion sources
  3. 2.3Dense plasma focus devices
  4. 2.4Accelerator-based D-Li sources
  5. 2.5IFMIF-DONES and its design
  6. 2.6Neutrons in tokamaks: JET and ITER
  7. 2.7Neutrons in inertial confinement: NIF
  8. 2.8Volumetric neutron sources
  9. 2.9Medical and industrial applications
  10. 2.10Case study: comparison of sources for materials testing
  1. 3.1Fission chambers and flux monitors
  2. 3.2Foil activation and spectrometry
  3. 3.3Time-of-flight spectrometers
  4. 3.4Diamond detectors
  5. 3.5Neutron cameras and tomography
  6. 3.6Calibration of neutron diagnostics
  7. 3.7Ion temperature measurements
  8. 3.8Neutron diagnostics at ITER
  9. 3.9Yield at NIF and its measurement
  10. 3.10Laboratory: analysis of an activation spectrum
  1. 4.1The Boltzmann transport equation
  2. 4.2Monte Carlo method and the MCNP and OpenMC codes
  3. 4.3FENDL nuclear libraries
  4. 4.4Calculating the tritium breeding ratio
  5. 4.5Nuclear heating in components
  6. 4.6Materials damage: dpa and gas production
  7. 4.7Shielding of superconducting magnets
  8. 4.8Activation and shutdown dose
  9. 4.9Nucleonics benchmarks at FNG and JET
  10. 4.10Laboratory: Monte Carlo model of a 14 MeV source
  1. 5.1Tritium breeding in blankets
  2. 5.2Materials testing with fusion neutrons
  3. 5.3Production of medical radioisotopes
  4. 5.4Waste transmutation
  5. 5.5Radiation protection in fusion facilities
  6. 5.6Activation of air and coolant
  7. 5.7Biological shielding requirements
  8. 5.8Required nuclear data and its gaps
  9. 5.9Neutron challenges for commercial power plants
  10. 5.10Case study: activation inventory of a component
  1. 6.1Defining the source and geometry
  2. 6.2Selecting nuclear data
  3. 6.3Building the transport model
  4. 6.4Flux and spectrum calculation
  5. 6.5Assessment of tritium, heat and damage
  6. 6.6Shielding and activation analysis
  7. 6.7Discussion of uncertainties
  8. 6.8Synthesis of results
  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 MCNP, OpenMC, FISPACT-II, Geant4, FLUKA, in free, academic or evaluation versions. Assessments are based on real procedures for foil activation dosimetry, neutron transport calculation in a blanket, and analysis of irradiation damage in materials. Assessment is continuous by module plus the final integrating project.

Accredited laboratories(EN ISO/IEC 17025) with a rotor bench, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented thesis:safety case, test plan, compliance dossier and operational 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, OT cyber, DIH and compliance as pillars.
Capstone project

Build it end to end

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

Defining the source and geometry

Explain the fusion reactions that produce neutrons and their spectra.

Selecting nuclear data

Describe fusion neutron sources and their applications.

Building the transport model

Apply neutron diagnostic techniques and activation dosimetry.

Flux and spectrum calculation

Calculate neutron transport with Monte Carlo codes.

Assessment of tritium, heat and damage

Evaluate the effects of neutrons on materials, activation and damage.

Career opportunities

Where this takes you

Fusion neutronics engineerPlasma diagnostics physicistNeutron dosimetry specialistFusion materials researcherRadiation protection technicianNeutron source 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 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 between 10 and 15 hours per week on average, compatible with a full-time job.

You will work with MCNP, OpenMC, FISPACT-II, Geant4, FLUKA. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An SEIUM diploma upon passing the continuous assessment and the integrating project. It 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 in the advanced programme. Check the recognition policy when you enrol.

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