Gateway for:

Member Countries


#0365Laser Driver Fusion Reactor

Experimental and Theoretical Modeling of a Pure and Safe High Efficiency Laser Driver Fusion Reactor.

#0390Space Nuclear System Simulation

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

#0610Simulation of New NPP

Calculation and Simulation Complex of New Generation Power Plant with B-407

#0858Computer Complex for Research Reactors

Multifunctional Computer Complex for Research Reactors

#0941Database on Fission Products Release

Creation of a Database for Computational Codes, Realizing Detailed Mathematical Modeling of a Radioactive Fission Products Realize from Fuel Rods VVER 440, VVER 1000

#1195Dynamic Simulator for Power Complex

A Multipurpose Dynamic Electric System Simulator for the RIAR Power Complex

#1288Safe Type of Transference for Spent Fuel

Safe Transference of Spent Fuel Assemblies from Near-Reactor Storage Pools to Long-term "Dry" Storage

#2105Boron Dilution in WWER Reactors

Study of Emergency Situations Related to Boron Dilution in WWER Reactors

#2560Data Uncertainty Influence on Reactor Parameters Variances

Development of the Basis for Neutron-Physical Calculations of Reactor Value Variances Caused with Uncertainties of Initial Data

#2561Simulator Based on Pulsed Nuclear Reactor

Simulator Based on Pulsed Nuclear Reactor BIR-2M and Kinetic Process Emulator in Real Time for Personnel Training Aimed at Higher Safety of Operations

#2815Spent Nuclear Fuel Dry Cask Storage

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

#2839Radiation-Induced Processes in Reactor Materials

Fundamental Studies of Radiation-Induced Processes for Production of Radiation Resistant Structural Materials for Fission and Fusion Reactors and Future Advanced Technologies

#3012Molten-Salt Reactor with Micro-Particle Fuel

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)

#3041Graphite Isotope Ratio Method

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

#3069Perturbation Theory in the Nuclear Power

Preparation of the Scientific Monograph "Perturbation Theory and Adjoint Function Method in the Problems of Nuclear Power"

#3176Nuclear Data for Minor Actinides

Measurement and Evaluation of Cross Section for Minor Actinides in Low Energy Region

#3267Computing Nuclear Reactor Cells

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

#3573Fuel Elements within Fast Pulse Reactors

Calculated, Theoretical and Experimental Substantiation of the Diagnostics Technique over the State of Typical Disc Fuel Elements within Fast Pulse Reactors

#3574Accelerator-Driven Systems for Transmutation

Comparative Study of ADS-burners with Fast, Intermediate and Thermal Neutron Spectrum for Radioactive Waste Transmutation