Part II – Deterministic modelling of nuclear reactor cores
Master nuclear core calculations: learn deterministic core physics methods, algorithms, assumptions, and limits through a flexible, expert-led 6‑week course.
About the course
The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes, either commercially available or developed in-house.
Over six weeks, you will learn the main algorithms used in such codes for modelling nuclear reactor cores using deterministic methods (also known as core calculations). The course is not about explaining how to use such software, rather to understand the underlying methods, together with their assumptions and limitations.
The course module combines access to a textbook, pre-recorded video lessons, quizzes, a course chatbot, and live sessions, giving you flexibility to learn at your own pace while benefiting from expert-led discussions and peer exchange.
The live sessions also include exercises on an industrial core physics code
After completing the course, you will be able to use deterministic core calculation codes knowing their approximations and limitations, giving you confidence in your future simulations.
Learning objectives
By the end of this course module, you will be able to:
- Formulate and manipulate the governing equations describing neutron transport, fluid dynamics and heat transfer under various theoretical frameworks.
- Differentiate the modelling strategies used for neutron transport, fluid dynamics and heat transfer.
- Weigh the limitations of the different modelling strategies.
- Use deterministic core physics solvers with confidence.
Content
Weeks 1-2:
Core concepts on transport phenomena in nuclear reactors (multi-physics/multi-scale aspects, neutron transport, fluid dynamics, heat transfer, modelling strategies, deterministic modelling)
Weeks 3-4:
Core concepts in neutron transport and thermal-hydraulic calculations at the core level (angular and spatial discretization of the neutron transport equation, determination of the steady-state and non-steady state core-wise solution, space- and time-averaged conservation equations for flow transport, flow models, spatial and temporal discretization of flow models, modelling of heat conduction in solid structures, neutronic/thermal-hydraulic coupling – spatial and temporal coupling)
Weeks 5-6:
Experiencing industrial deterministic core calculations (input deck preparation, code running, results interpretation)
Schedule
Week 1: Kick-off
October 9, 2026, 13:00 – 15:00 (CEST), Online, Zoom (also recorded)
Week 2: Wrap-up on transport phenomena + Q&A
October 15, 2026, 13:00 – 16:00 (CEST), Online, Zoom (also recorded)
Break to allow attending the course module “Deterministic modelling of nuclear fuel assemblies”
Week 3: Wrap-up on core calculations + Q&A
November 30, 2026, 13:00 – 16:00 (CET), Online, Zoom (also recorded)
Week 5: workshop on using a deterministic core physics code
December 7, 2026, 13:00 – 16:00 (CET), Online, Zoom (also recorded)
Week 6: workshop on using a deterministic core physics code
December 14, 2026, 13:00 – 16:00 (CET), Online, Zoom (also recorded)
Language of Instruction
English
Price
Free for students
For professionals from developed countries: 16400 SEK excl. VAT
For professionals from emerging countries: 2640 SEK excl. VAT
Lecturer
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Course Participant profile
This course module is designed for:
- MSc students, PhD students and Post-Doc students having some solid background knowledge in nuclear engineering.
- Nuclear engineers.
- Reactor physicists.
- Nuclear safety analysts.
- Research scientists in the above fields.
The course does not describe the physical phenomena occurring in nuclear reactors – the course focuses instead on how to model such phenomena in simulation platforms. It is therefore highly recommended that the course participants already have some previous solid knowledge in reactor physics or nuclear engineering.
The course nevertheless presents the derivation of all balance equations of importance from first principles. This allows the participants not familiar with reactor modelling to comprehend all concepts thoroughly