(in Polish) Zaawansowane warsztaty z fizyki reaktorów jądrowych 1100-FRJ
The course focuses on the preparation of nuclear data for mathematical modeling in reactor physics, analytical and numerical solutions of the neutron transport equation in reactor systems, application of statistical methods in reactor physics, fuel burnup modeling, and sensitivity and uncertainty analysis related to nuclear data. The course also covers the coupling of neutron and thermal-hydraulic codes.
Main fields of studies for MISMaP
Prerequisites (description)
Course coordinators
Learning outcomes
Students gain advanced skills in mathematical modeling and analysis of neutron processes in nuclear reactors, including interpretation of simulation results and assessment of the impact of nuclear data on calculation outcomes.
Assessment criteria
Completion is based on a report or course project, considering correctness of data preparation, execution of simulations, and interpretation of results.
Practical placement
n/a
Bibliography
Course literature is provided by instructors according to the course topics.
Additional information
Additional information (registration calendar, class conductors, localization and schedules of classes), might be available in the USOSweb system: