Part III – Deterministic multiphysics modelling hands-on
Nuclear reactor modelling spans complex physics and scales. Through this course, you will develop simulation solvers and algorithms for reactor systems via hands-on programming.
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 five consecutive days, you will implement some of the main algorithms in a dedicated simulation environment. You will more specifically develop: a collision probability module, a multi-group diffusion-based core solver, a fluid dynamic solver using the Homogeneous Equilibrium Model, a pin temperature solver, a monolithic multiphysic wrapper. Examples will tackle both a Light Water Reactor system, and a Sodium-cooled Fast Reactor system.
The course module combines group discussions and quizzes on the previous course modules (“Deterministic modelling of nuclear fuel assemblies” and “Deterministic modelling of nuclear reactor cores”), and programming assignments using Matlab Grader (platform provided to you as part of the course).
After completing the course, you will be able to implement some of the main modelling strategies used for modelling nuclear fuel assemblies and cores in simulation environments.
Learning objectives
By the end of this course module, you will be able to:
- Formulate and implement algorithms for modelling neutron transport and thermal-hydraulics at both the fuel assembly and core levels
- Design efficient numerical algorithms
- Solve large systems of linear and non-linear equations.
- Construct multi-physics solvers using monolithic approaches
Content
Days 1 and 2:
Transport phenomena and neutron transport at the cell and assembly levels
Day 3:
Neutron transport at the core level
Day 4:
Thermal-hydraulics
Day 5:
Neutronic/thermal-hydraulic coupling
Schedule
Day 1:
Wrap-up on transport phenomena and neutron transport at the cell and assembly levels + Q&A + programming assignment on pin cell calculations
January 11, 2027, 09:00 – 17:30 (CET), Onsite or online via Zoom (also recorded)
Day 2:
Wrap-up on neutron transport at the cell and assembly levels + Q&A + programming assignment on pin cell calculations
January 12, 2027, 09:00 – 17:30 (CET), Onsite or online via Zoom (also recorded)
Day 3:
Wrap-up on neutron transport at the core level + Q&A + programming assignment on core calculations
January 13, 2027, 09:00 – 17:30 (CET), Onsite or online via Zoom (also recorded)
Day 4:
Wrap-up on thermal-hydraulics at the core level + Q&A + programming assignment on flow transport and pin temperature modelling
January 14, 2027, 09:00 – 17:30 (CET), Onsite or online via Zoom (also recorded)
Day 5:
Wrap-up on neutronic/thermal-hydraulic coupling + Q&A + programming assignment on mutliphysic integrated solvers
January 15, 2027, 09:00 – 17:30 (CET), Onsite or online via Zoom (also recorded)
Format
The sessions can be attended onsite at Chalmers University of Technology or fully online.
Price
Free for students
For professionals from developed countries: 8200 SEK excl. VAT
For professionals from emerging countries: 1320 SEK excl. VAT
Language of instruction
English
Lecturer
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Course Participant profile
- 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.
Please note that you are only allowed to take this course if you have finished Part I and Part II of the course first.