Experimental and Theoretical Modeling of a Pure and Safe High Efficiency Laser Driver Fusion Reactor.
Development of the Simulation Methods for the Space Nuclear Power Systems in Support of International Projects (Pioner).
#0543Heat Exchange Codes
Development of Techniques and Codes for Numerical Solution of 2D and 3D Radiant Heat Exchange Problems with the Zonal Method Using View Factors
Calculation and Simulation Complex of New Generation Power Plant with B-407
Multifunctional Computer Complex for Research Reactors
Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000
A Multipurpose Dynamic Electric System Simulator for the RIAR Power Complex
Safe Transference of Spent Fuel Assemblies from Near-Reactor Storage Pools to Long-term "Dry" Storage
Study of Emergency Situations Related to Boron Dilution in WWER Reactors
Development of the Basis for Neutron-Physical Calculations of Reactor Value Variances Caused with Uncertainties of Initial Data
Simulator Based on Pulsed Nuclear Reactor BIR-2M and Kinetic Process Emulator in Real Time for Personnel Training Aimed at Higher Safety of Operations
Development of Software for Numerical Analysis of Fuel Temperature States and Heat- and Mass-Transfer Processes in RBMK-1000 SNF Casks at the Main Steps of Preparing Fuel to Dry Long-Term Storage, Numerical Studies
Fundamental Studies of Radiation-Induced Processes for Production of Radiation Resistant Structural Materials for Fission and Fusion Reactors and Future Advanced Technologies
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)
Verification of Graphite Isotope Ratio Method to Restore Neutron Local Fluence in Reactor Core with Graphite Moderator by the Example of the Reactor of the First A-Plant in Obninsk to Control Non-Proliferation of Nuclear Fissile Materials
Preparation of the Scientific Monograph "Perturbation Theory and Adjoint Function Method in the Problems of Nuclear Power"
Measurement and Evaluation of Cross Section for Minor Actinides in Low Energy Region
Development of Calculation Methodology Used in Computing Nuclear-Physics Characteristics of Nuclear Reactor Cells and Assemblies Containing MOX Fuel, and in Unstructured Grids for Nuclear Safety of Reactor Facilities
Calculated, Theoretical and Experimental Substantiation of the Diagnostics Technique over the State of Typical Disc Fuel Elements within Fast Pulse Reactors
Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation