I teach courses in nuclear engineering at both undergraduate and graduate levels:

Introduction to nuclear reactor theory (undergraduates)

The course provides a comprehensive foundation in the physics, engineering principles, and safety considerations underlying nuclear reactors. The course covers the neutron life cycle in a reactor core, chain reactions, diffusion theory, and key physical and thermo-hydraulic design concepts of existing and advanced reactor systems. Additional topics include the nuclear fuel cycle, reactor safety, environmental aspects, and issues related to non-proliferation. The course is designed for senior undergraduate students in engineering and the natural sciences, as well as for graduate students who require prerequisite knowledge for advanced studies in nuclear engineering.

Physics of nuclear reactors (graduates)

A graduate-level course that provides a rigorous foundation in the physics governing neutron behavior and reactor operations. The course covers the full neutron life cycle, neutron-matter interactions, scattering and thermalization, diffusion and transport theory, multigroup methods, reactor kinetics, reactivity feedbacks, and fuel burnup. Students develop a deep understanding of the physical principles and mathematical models that underpin reactor design, safety, and control. Topics such as delayed neutrons, point kinetics, burnable poisons, and xenon–samarium transients are treated in detail. Taught in English, the course is intended for students with background in engineering or the natural sciences and emphasizes both physical intuition and analytical formulation through weekly three-hour lectures.

Neutron transport theory (graduates)

An advanced graduate-level course that provides a comprehensive foundation in the mathematical and physical principles underlying neutron transport in nuclear systems. The course covers the integro-differential and integral forms of the neutron transport equation, coordinate system formulations, singular eigenmodes, spherical harmonics, and diffusion approximations, as well as the discrete ordinates method. Additional topics include the adjoint transport equation, importance functions, perturbation theory, and time-dependent transport. Emphasis is placed on building physical intuition alongside rigorous analytical treatment, enabling students to understand, derive, and apply the fundamental tools used in modern reactor physics and radiation transport analysis.

Advanced topics in reactor physics (graduates)

A graduate-level course that provides an in-depth exploration of the physics, design principles, and dynamic behavior of fission reactor systems. The course covers the energetics of nuclear reactions, radiation-matter interactions, radioactivity, and the fundamental principles of reactor operation. Students study core subjects such as chain reactions, reactor statics and kinetics, multigroup analysis, and thermal-hydraulics, alongside specialized topics including xenon and samarium dynamics, fuel burnup, reactivity coefficients, and flux-dependent safety effects. Emphasis is placed on developing both the physical intuition and mathematical formulation essential for analyzing and designing modern reactor systems.

Numerical analysis for nuclear engineering (graduates)

A graduate-level course designed to provide students with both theoretical understanding and practical skills in numerical methods used to solve problems in nuclear science and engineering. The course covers solutions of ordinary and partial differential equations, eigenvalue problems, and nonlinear systems, with direct applications to radioactive decay chains, fuel burnup calculations, neutron diffusion, reactor kinetics, and Monte Carlo methods for radiation transport. Throughout the semester, students learn to implement numerical algorithms, develop scientific code in Python, and analyze computational results, with emphasis on understanding the underlying models and their relevance to real nuclear systems.