CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course on Hybrid Fission-Fusion Power Generation

Online course of 300 h in Hybrid Fission-Fusion Power Generation. 6 modules covering ASME BPVC Section III, Division 4 (fusion energy device components), IAEA SSR-2/1 (Rev. 1) (safety of nuclear power plants: design) and MCNP. Dedicated tutor and enrolment open.

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 concept of a fission-fusion hybrid system and its applications.

02

Calculate the neutronic parameters of a subcritical blanket.

03

Analyse the fusion source requirements for a hybrid system.

04

Evaluate thermal-hydraulic behaviour and energy conversion.

05

Identify the specific safety, waste and safeguards aspects.

06

Apply neutron transport and activation tools.

07

Develop a conceptual design of a hybrid system.

Profile

Who it's for

  • Neutronics engineer looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Advanced reactor design engineer looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Nuclear fusion researcher looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Thermal-hydraulics engineer looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Nuclear safety analyst looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Licensing specialist looking to specialise in Hybrid Fission-Fusion Power Generation.
  • Engineering or science graduates looking to move into fusion research.
Standards & tools

What you'll work with

  • ASME BPVC Section III, Division 4 (fusion energy device components)
  • IAEA SSR-2/1 (Rev. 1) (safety of nuclear power plants: design)
  • ANSI/ANS-8.1 (nuclear criticality safety outside reactors)
  • IAEA GSR Part 4 (Rev. 1) (safety assessment)
  • Directive 2014/87/Euratom (nuclear safety)
  • IAEA GSR Part 5 (predisposal management of radioactive waste)
  • INFCIRC/153 (safeguards)
Syllabus

6 modules · 300 h

  1. 1.1History of the concept: the proposals of Bethe and Sakharov
  2. 1.2Fusion neutron source and subcritical blanket
  3. 1.3Energy multiplication in the blanket
  4. 1.4Fusion Q factor required in a hybrid
  5. 1.5Comparison with ADS systems
  6. 1.6Applications: energy, transmutation and fuel breeding
  7. 1.7Current debate and programmes in China and Russia
  8. 1.8Advantages and limitations versus pure fission
  9. 1.9Non-proliferation aspects of the hybrid
  10. 1.10Case study: energy balance of a conceptual hybrid
  1. 2.1Subcritical multiplication factor ks
  2. 2.2The 14 MeV spectrum and threshold reactions
  3. 2.3Multiplication by (n,2n) and fast fission
  4. 2.4External source and gain calculation
  5. 2.5Fuels: uranium, thorium and minor actinides
  6. 2.6Tritium breeding in the blanket
  7. 2.7Burn-up and isotopic evolution
  8. 2.8Transport codes for hybrid blankets
  9. 2.9Validation with blanket experiments
  10. 2.10Lab: multiplication calculation with a simplified model
  1. 3.1Compact tokamak as a neutron source
  2. 3.2Magnetic mirrors and linear configurations
  3. 3.3Inertial confinement fusion sources
  4. 3.4Neutron wall loading
  5. 3.5Availability and load factor
  6. 3.6FDS designs from China's ASIPP
  7. 3.7Livermore's LIFE concept
  8. 3.8Georgia Tech's SABR design
  9. 3.9Source-blanket geometric interaction
  10. 3.10Practice: sizing a neutron source for a blanket
  1. 4.1Coolants: helium, sodium, lead-lithium and salts
  2. 4.2Heat extraction from the blanket
  3. 4.3Power distribution and density peaks
  4. 4.4Brayton and Rankine power cycles
  5. 4.5Balance of plant and recirculating power
  6. 4.6Net system efficiency
  7. 4.7Decay heat management
  8. 4.8Compatible structural materials
  9. 4.9Magnetohydrodynamic coupling
  10. 4.10Case study: balance of plant of a 1000 MWt hybrid
  1. 5.1Inherent safety of the subcritical system
  2. 5.2Loss-of-source transients
  3. 5.3Radioactive inventory compared with a fission reactor
  4. 5.4Transmutation of minor actinides
  5. 5.5Tritium inventory and confinement
  6. 5.6Safeguards applied to the hybrid
  7. 5.7Fission and fusion regulatory frameworks
  8. 5.8Economics and feasibility of the concept
  9. 5.9Critical assessment and alternatives
  10. 5.10Workshop: comparative safety analysis
  1. 6.1Defining the hybrid's mission
  2. 6.2Selecting the fusion source
  3. 6.3Blanket and fuel design
  4. 6.4Neutronic multiplication calculation
  5. 6.5Energy and thermal-hydraulic balance
  6. 6.6Safety and waste analysis
  7. 6.7Feasibility assessment
  8. 6.8Design summary
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

100% online training on the SEIUM campus, with downloadable materials, recorded classes and a dedicated technical tutor. No fixed timetable: students progress at their own pace within the intake period, making it easy to combine with work.

Each module combines theory, guided reading of the original standards and applied exercises. The software used is MCNP, Serpent, OpenMC, FISPACT-II, COMSOL Multiphysics, in free, academic or trial versions. Testing is studied through real procedures from neutronic calculation of a subcritical blanket, energy balance of a hybrid system, actinide transmutation analysis. Assessment is continuous for each module, plus a final capstone project.

Accredited laboratories(EN ISO/IEC 17025) with a rotor test rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-driven Master's Thesis: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:safety-by-design approach, OT cybersecurity, 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 hybrid's mission

Explain the concept of a fission-fusion hybrid system and its applications.

Selecting the fusion source

Calculate the neutronic parameters of a subcritical blanket.

Blanket and fuel design

Analyse the fusion source requirements for a hybrid system.

Neutronic multiplication calculation

Evaluate thermal-hydraulic behaviour and energy conversion.

Energy and thermal-hydraulic balance

Identify the specific safety, waste and safeguards aspects.

Career opportunities

Where this takes you

Neutronics engineerAdvanced reactor design engineerNuclear fusion researcherThermal-hydraulics engineerNuclear safety analystLicensing specialist
Admissions & scholarships

Requirements

  • No previous qualification is required.
  • An internet connection and a computer able to run the programme software.
  • A level of 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 300 hours spread over 3 to 5 months. That is an average of 10 to 15 hours per week, compatible with a full-time job.

You will work with MCNP, Serpent, OpenMC, FISPACT-II, COMSOL Multiphysics. Free, academic or trial versions are used, and your tutor will point out a free alternative where one exists.

A SEIUM Institute diploma, awarded on passing the continuous assessment and the capstone project. It is SEIUM's own qualification, not an official state-accredited degree.

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

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