CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course in Uncertainty Analysis in Nuclear Simulation

Online 300-hour course in uncertainty analysis in nuclear simulation. 6 modules covering NRC RG 1.203 (transient and accident analysis methods, EMDAP), NRC RG 1.157 (ECCS best-estimate calculations) and DAKOTA. Assigned 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

Identify the sources of uncertainty in nuclear models and data.

02

Apply statistical propagation methods such as Monte Carlo and Wilks.

03

Quantify uncertainty in neutronics calculations derived from nuclear data.

04

Evaluate uncertainty in thermal-hydraulic simulations of transients.

05

Carry out local and global sensitivity analyses.

06

Integrate the BEPU methodology into a safety analysis.

07

Document uncertainty results in accordance with regulatory guides.

Profile

Who it's for

  • Uncertainty analyst in nuclear simulation who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • BEPU safety analysis engineer who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • Specialist in code verification and validation who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • Neutronics engineer who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • Thermal-hydraulics engineer who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • Researcher in uncertainty quantification who wants to specialise in Uncertainty Analysis in Nuclear Simulation.
  • Graduates in engineering or science seeking to enter nuclear power plants.
Standards & tools

What you'll work with

  • NRC RG 1.203 (transient and accident analysis methods, EMDAP)
  • NRC RG 1.157 (ECCS best-estimate calculations)
  • IAEA SSG-2 (deterministic safety analysis)
  • 10 CFR 50.46 (ECCS acceptance criteria)
  • ASME V&V 20 (verification and validation in CFD and heat transfer)
  • IAEA GSR Part 4 (safety assessment of facilities)
Syllabus

6 modules · 300 h

  1. 1.1Aleatory versus epistemic uncertainty
  2. 1.2Sources: nuclear data, models and geometry
  3. 1.3Propagation versus sensitivity
  4. 1.4BEPU versus conservative approach
  5. 1.5Verification, validation and uncertainty quantification (VVUQ)
  6. 1.6NRC Regulatory Guide 1.203
  7. 1.7CSAU methodology
  8. 1.8Input probability distributions
  9. 1.9Expert judgement and elicitation
  10. 1.10Workshop: identifying uncertainties in a transient
  1. 2.1Simple Monte Carlo sampling
  2. 2.2Latin Hypercube Sampling
  3. 2.3Wilks' formula and 95/95 tolerance
  4. 2.4Order statistics
  5. 2.5Perturbation methods
  6. 2.6Polynomial chaos expansion
  7. 2.7Surrogate models and kriging
  8. 2.8Bayesian methods
  9. 2.9Convergence and number of samples
  10. 2.10Practice: applying Wilks' formula
  1. 3.1Covariance matrices of nuclear data
  2. 3.2ENDF/B-VIII and JEFF-3.3 libraries
  3. 3.3Generalised perturbation theory
  4. 3.4SCALE's SAMPLER tool
  5. 3.5Total Monte Carlo method
  6. 3.6Uncertainty in keff and reactivity
  7. 3.7Propagation in burn-up calculations
  8. 3.8OECD/NEA UAM benchmark
  9. 3.9Data adjustment with integral experiments
  10. 3.10Laboratory: keff uncertainty with SCALE
  1. 4.1Uncertain parameters in system codes
  2. 4.2Heat transfer correlations
  3. 4.3OECD BEMUSE programme
  4. 4.4PREMIUM project on inverse quantification
  5. 4.5DAKOTA and URANIE tools
  6. 4.6GRS method with SUSA
  7. 4.7Peak cladding temperature and margins
  8. 4.8Effect of nodalisation and user
  9. 4.9Validation with integral test facilities
  10. 4.10Case study: large LOCA with the BEPU method
  1. 5.1Pearson and Spearman correlation coefficients
  2. 5.2Sobol indices
  3. 5.3Morris method
  4. 5.4Parameter importance analysis
  5. 5.5Dimensionality reduction
  6. 5.6Visualisation of results
  7. 5.7Communicating uncertainties to the regulator
  8. 5.8Safety margins and acceptance
  9. 5.9Multiphysics coupling of uncertainties
  10. 5.10Practice: Sobol indices in a thermal model
  1. 6.1Scenario selection and figure of merit
  2. 6.2Identification of uncertain parameters
  3. 6.3Assignment of distributions
  4. 6.4Sampling design
  5. 6.5Execution of calculations
  6. 6.6Statistical analysis 95/95
  7. 6.7Sensitivity analysis
  8. 6.8Conclusions on margins
  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 material, recorded classes and an assigned technical tutor. No fixed timetables: students progress at their own pace within the enrolment period, which makes it compatible with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is DAKOTA, SUSA (GRS), RAVEN (INL), SCALE (Sampler/TSUNAMI), Python (SALib), in free, academic or evaluation versions. The tests are studied using real procedures from Monte Carlo propagation campaigns, global sensitivity analysis of transients, and comparison with experimental databases. Assessment is continuous per 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-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 cyber-security, 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.

Scenario selection and figure of merit

Identify the sources of uncertainty in nuclear models and data.

Identification of uncertain parameters

Apply statistical propagation methods such as Monte Carlo and Wilks.

Assignment of distributions

Quantify uncertainty in neutronics calculations derived from nuclear data.

Sampling design

Evaluate uncertainty in thermal-hydraulic simulations of transients.

Execution of calculations

Carry out local and global sensitivity analyses.

Career opportunities

Where this takes you

Uncertainty analyst in nuclear simulationBEPU safety analysis engineerSpecialist in code verification and validationNeutronics engineerThermal-hydraulics engineerResearcher in uncertainty quantification
Admissions & scholarships

Requirements

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

FAQ

Frequently asked questions

The programme totals 300 hours spread over 3 to 5 months. That is between 10 and 15 hours a week on average, compatible with full-time work.

You will work with DAKOTA, SUSA (GRS), RAVEN (INL), SCALE (Sampler/TSUNAMI), Python (SALib). Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An SEIUM own diploma upon passing the continuous assessment and the integrating project. It is in-house training, not an official Ministry qualification.

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

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