The PhD program in the specialty "Nuclear Energy Installations and Facilities" aims to prepare scientific personnel and specialists in the field of nuclear energy – a field with a very broad scope and wide range of applications. Such specialists are needed by higher education institutions where physicists, engineering physicists, and engineers are trained, as well as by research institutes, nuclear power plants, state and private enterprises involved in nuclear energy and nuclear technologies. Nuclear reactors are directly related to national priorities for the safe and economical operation of nuclear power plants and the protection of the environment from radiation pollution. Internationally, these are priorities of the European Commission, the International Atomic Energy Agency, NATO, and others. The methods, models, and their use in describing physical processes in reactor systems lie at the foundation of all modern nuclear physics and applied mathematics, and their application in practice. From this perspective, the PhD program in this specialty means studying modern physical and mathematical methods and their application to obtain new results for reactor technologies.

Dissertation topics are mainly related to objects, systems, and facilities in the field of Nuclear Power Plants (NPPs) and are mostly dictated by practical needs. Of significant importance are topics related to nuclear and radiation safety, thermal-hydraulic analyses, nuclear fuel research, and modern projects for nuclear energy and non-energy facilities. Reviews of the scientific and practical contributions of dissertations have been received not only from our institutes and industrial enterprises but also from leading scientific organizations and firms abroad.

The developed dissertation topics cover various areas of nuclear systems and facilities, such as:

"Study of severe accidents in NPPs with VVER-type reactors"
"Analysis of design-basis and beyond-design-basis accidents in NPPs with VVER reactors"
"Three-dimensional simulation modeling of the behavior of NPPs with VVER-type reactors under accident conditions"
"Analysis and management of severe accidents in units with VVER-1000/V320 reactors"
"Uncertainty analysis of results from thermal-hydraulic calculations of accident conditions for VVER-1000 reactors"
 Modeling and Analysis of Internal Flooding in NPPs with VVER Reactors
Models and Algorithms for Power Control of VVER (PWR) Reactors
Modeling and Analysis of Thermal-Hydraulic and Accident Processes in the Core of Pressurized Water Reactors