Development, Calculation and Experimental Validation of the Lead-Cooled Fast Reactor Concept (including the Comparison of Critical and Subcritical Reactor with External Proton Source)
Designing of the Specialized Small-Sized Medical Reactor for Neutron- and Neutron-Capture Therapy
Hybrid Reactor (TEC-NIT) Conceptual Design Development
Shut down Reactor Transformation into Subcritical Neutron Source. Control and Safety System Substantiation and Development.
Development and Computational-Experimental Validation of the Concept of Self-Quenching Multi-channel Pulse Graphite Reactor (MIGR) for the Studies on Nuclear Reactor Safety.
Development of the Physical Substantiations of Electronuclear Power Installation.
Analysis of Accident Evolution and Consequences for the 4th Block Chernobyl Nuclear Power Plant.
Development of Construction Concepts for Computerized Control, Monitoring and Diagnostic System for Nuclear Power Plants with Improved Safety.
#0695EOS Reactor Fuel
Development of the Equations of State for Fuel Compositions, which Take into Account the Microstructure Accumulation Kinetics its Use for Simulation of the Fuel Failure Consequences in Nuclear Reactors of VariousType. (Continuation of the project 003)
Analysis of Perspective Technical Solutions of Nuclear Power Facilities on the Basis of Patent Information Study.
Design, Manufacture and Test of the Prototypes of Accelerating Structures for Reliable Radiation-clean High Power Proton Linac
Start-up, Neutron Fueling and Material Problems of a Spherical Tokomak reactor
Thermonuclear Amplificator of Neutrons by Fission Fragments (THERANFF)
Experimental Study of Fast and Fast-Thermal Accelerator Driven Systems on the Basis of BFS-1 – Microtron Complex
Nuclear Lagoon for Biomass Photosynthesis with Use of Radioluminescent Radiation of Nuclear-Optical Converter
Analysis, Substantiation and Agreeing of Innovative Reactor Technologies and Fuel Cycles Acceptability Criteria: Nuclear, Radiation and Environmental Safety, Economics and Non-Proliferation
Research and Development of an Optimal Neutron Moderators Configuration for IBR-2M Pulsed Neutron Source
Innovative Concept Development for Solid Coolant Reactor of Generation IV
Liquid Metal Coolant for High-Temperature Fast Reactors
Calculational-Theoretical and Design Studies, Preparation of Experimental Works on the Substantiation of the Conceptual Design of Small Power Installation MARS (Autonomous Molten-Salt Reactor with Micro-Particle Fuel)