I teach nuclear science & engineering courses at both undergraduate and graduate levels, covering reactor physics, neutron transport, and computational methods.

• Introduction to nuclear reactor theory (undergraduate)

This course provides a comprehensive foundation in the physics, engineering principles, and safety considerations underlying nuclear reactors. Topics include 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 subjects include the nuclear fuel cycle, reactor safety, environmental aspects, and non-proliferation considerations. The course is intended for senior undergraduate students in engineering and natural sciences, as well as for graduate students who require prerequisite knowledge for advanced studies in nuclear engineering.

• Physics of nuclear reactors (graduate)

This graduate-level course provides a rigorous foundation in the physics governing neutron behavior and reactor design and operation. The course covers 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 underpinning reactor design, safety, and control. Topics such as delayed neutrons, point kinetics, burnable poisons, and xenon-samarium transients are treated in detail. The course is intended for students with a background in engineering or the natural sciences, emphasizing physical intuition and analytical formulation.

• Neutron transport theory (graduate)

An advanced graduate-level course focused on the mathematical and physical foundations of neutron transport in nuclear systems. The course covers the integro-differential and integral formulations of the neutron transport equation, coordinate system representations, singular eigenmodes, spherical harmonics, diffusion approximations, and the discrete ordinates method. Additional topics include the adjoint transport equation, importance functions, perturbation theory, and time-dependent transport. Emphasis is placed on developing physical intuition alongside rigorous analytical treatment, enabling students to derive, interpret, and apply the fundamental tools of modern reactor physics and radiation transport analysis.

• Advanced topics in reactor physics (graduate)

This course provides an in-depth exploration of the physics, design principles, and dynamic behavior of fission reactor systems. Topics include nuclear reaction energetics, radiation-matter interactions, radioactivity, reactor statics and kinetics, multigroup analysis, and thermal-hydraulics. Advanced subjects such as zero-power experiments (e.g., neutron noise), full-power experiments (e.g., rod-drop, neutron activation analysis), xenon and samarium dynamics, fuel burnup, reactivity coefficients, and flux-dependent safety effects are also covered. The course emphasizes the development of physical intuition and mathematical formulation essential for analyzing and designing modern reactor systems.

• Numerical analysis for nuclear engineering (graduate)

This graduate-level course equips students with theoretical understanding and practical skills in numerical methods used in nuclear science and engineering. Topics include numerical 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. Students implement numerical algorithms, develop scientific code in Python, and critically analyze computational results, with emphasis on the connection between numerical models and real nuclear systems.