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FEI (IPPE)

General information

Full Name
FSUE State Scientific Center of the Russian Federation – Institute for Physics and Power Engineering named after A.I. Leypunsky (SSC IPPE)


Address
1, Bondarenko Sq., Obninsk, Kaluga reg., Russian Federation, 249033


Phone
7+48439+98250


Email
AVZROD@ippe.ru;


WWW
www.ippe.ru;


ISTC Projects

  • 0017 - Plutonium Conversion
  • 0018 - Reactor Pumped Laser for ICF
  • 0040 - Nuclear Materials Accounting
  • 0085 - Radiation Ambient Monitoring
  • 0116 - Verification of Reactor Data Bases (R)
  • 0153-2 - Thermovision Monitors for Nuclear Reactors
  • 0180 - Non-Uniform Shielding of Fusion Reactors
  • 0220 - Fast Sodium Reactors
  • 0304 - Accelerator-Based Measurements of Minor Actinides Cross-Sections
  • 0336 - Reactor for Neutron Therapy
  • 0369 - Economics of Plutonium Burn
  • 0371 - Pu-Utilization in LWR Experiments
  • 0371-2 - Pu-Utilization in LWR Experiments
  • 0559 - Lead-Bismuth Target
  • 0564 - Temperature of Water-cooled Reactor
  • 0650 - Safety of Advanced Fast Reactors
  • 0723-2 - Recycling Weapon-grade U and Pu in U-Th Closed-cycle Reactors
  • 0731 - Benchmark Data on Gamma-ray Production for Fusion Reactors
  • 0733 - Al Oxide Aerogel Production
  • 0777 - Production of Radionuclides and Radiopharmaceuticals
  • 0779 - Dismantling of BR-10 Fast Reactor
  • 0815.2 - Codes for Nuclear Safety Evaluation
  • 0816 - Super-Intensive Neutron Source
  • 0828 - Molybdenium Extraction from Reactor Fuel
  • 0910 - Nuclear Data of Vanadium
  • 0910.2 - Nuclear Data for Vanadium
  • 0916 - High Pure Radioisotopes
  • 0941 - Database on Fission Products Release
  • 0962 - Alpha-Emitting Radionuclides for Medicine
  • 0969 - Neutron Data for Thorium Cycle
  • 1002 - Treatment of Eye Cancer
  • 1015 - Environmental Impact of Fuel Cycles with Plutonium
  • 1049 - Nuclear Level Density Studies
  • 1059 - Neutron Therapy
  • 1070 - Low-Radiation Vanadium-Based Alloys
  • 1097 - SIC/SIC Composite
  • 1130 - Ceramic Composite Materials
  • 1143 - Terminology Glossary for Nuclear Material Safety
  • 1193 - Fuel Materials with Non-Uranium Diluent
  • 1246 - Nondestructive Burnup Measurements
  • 1321 - ROX-Fuel Fabrication
  • 1345 - Radioactive Targets
  • 1346 - Microbial Conditions in Spacecraft
  • 1347 - Lithium Detector of Solar Neutrinos
  • 1356 - Model for Nuclear Materials Control and Accounting
  • 1372 - Transmutation Effectiveness of Nuclear Waste
  • 1405 - Proton Induced Fission Cross Sections
  • 1411 - Simulation of Reactor Core Accidents
  • 1431 - Intensive Neutrino Source
  • 1443 - Plutonium Utilization Scenarios
  • 1484 - Accelerator Source for Neutron Therapy
  • 1537 - ISO Compatible Product Data Base
  • 1595 - Sorption Membranes for Waste Solidification
  • 1596 - Aluminium Industry Waste Reprocessing
  • 1611 - Thermohydraulics in Liquid Metal Cooled Reactors
  • 1749 - Fission Cross Sections for Minor Actinides
  • 1755 - Experimental Modeling of Accelerator - Blanket System
  • 1767 - Liquid Metal Coolant Disposal
  • 1796 - Nuclear Data for Astrophysics
  • 1821 - Monograph on Coupled Pulsed Reactor Systems
  • 1857 - Informational Technologies for Export Control System
  • 1886 - Endurance of Accelerator Beam Window
  • 1931 - Oxide Nanoparticles in Lead Melt
  • 1954 - Fissile Materials Identification Device
  • 1969 - Neutron Therapy at the Nuclear Reactors
  • 2025 - Radiation Sources for Brachytherapy
  • 2036 - Lithium Circulation Loop and Lithium Neutron Target
  • 2048 - Improvement of Steels Corrosion Resistance
  • 2199 - Neutron Cross-Sections and Level Density for Fission-Products, Th, 233-U
  • 2253 - Investigation of the Delayed Neutron Characteristics
  • 2253.2 - Investigation of the Delayed Neutron Characteristics
  • 2306 - Rectifier on a Heat-into-Electricity Thermionic Converter Basis
  • 2569 - Neutron Source for Boron Neutron Capture Therapy
  • 2573 - Laser Separation of Lead Isotopes
  • 2582 - Actinides Transmutation Study at Critical Assembly
  • 2603 - A Database of Critical Experiments
  • 2607 - Scission Neutrons in Low Energy Fission
  • 2650 - High Activity Generator for Radiotherapy
  • 2659 - Optical Fibers under Irradiation
  • 2661 - Reactors with Lead Сoolant
  • 2680 - Minor Actinide Transmutation in Nitrides Fuel Environment
  • 2689 - Supercritical Pressure Water for Nuclear Power Engineering
  • 2695 - Bi-213 Generator for Radiotherapy
  • 2698 - Tungsten Nuclear Data
  • 2711 - Neutron Induced Total Fission Cross Sections
  • 2769 - Aggregation of Shungite Carbon Nanoparticles
  • 2786 - Radionuclide Migration in Polluted Areas
  • 2787 - Moderators for Pulsed Neutron Source
  • 2862 - Low Dose Radiation Effect on Cancer Risk
  • 2884 - Minor Actinides Cross-Sections
  • 2911 - Power Fast Reactor Radioactive Sodium
  • 2918 - Civilian Nuclear Power Technology and Nuclear Weapons Proliferation
  • 2979 - Local Radiofrequency Hyperthermia
  • 3020 - Control of Oxygen Content in Lead Coolants
  • 3031 - Conditioning Middle-Active Liquid Wastes into Matrix
  • 3041 - Graphite Isotope Ratio Method
  • 3069 - Perturbation Theory in the Nuclear Power
  • 3094 - Control of subcriticality of neutron multiplying systems
  • 3099 - Purification of Sodium Coolant
  • 3239 - Experiments for Lead Cooled Reactors
  • 3297 - Targets for Neutron-Rich Nuclei Investigation
  • 3354 - Lithium Target for International Fusion Materials Irradiation Facility
  • 3392 - Microbiological Safety of Space Equipment
  • 3437 - Pulse Generator for Cancer Treatment
  • 3544 - Validation of Neutron Data of Structural Materials
  • 3608 - Minor Actinide Transmutation in Inert Matrices Fuels
  • 3679 - Hydrogen Production
  • 3698 - Radiation Sources for Therapy of Tumors
  • 3760 - Immobilization of High-Level Wastes
  • 3891 - Biomimetics for Detection of Air Pollutants
  • 4026 - Thermionic Converter Based Rectifier
  • A-1209 - Geocement binding materials for radioactive waste immobilization
  • A-1749 - Geocement Binders for Liquid Radioactive Waste
  • B-175 - Conception of Light Water Reactors

Tech areas

  • Radioactive Waste Treatment / Environment
  • Optics and Lasers / Physics
  • Nuclear Safety and Safeguarding / Fission Reactors
  • Monitoring and Instrumentation / Environment
  • Reactor Engineering and NPP / Fission Reactors
  • Modelling / Fission Reactors
  • Measuring Instruments / Instrumentation
  • Other / Fusion
  • Reactor Concept / Fission Reactors
  • Other / Other
  • Nuclear and Other Technical Data / Fission Reactors
  • Fuel Cycle / Fission Reactors
  • Nuclear Instrumentation / Fission Reactors
  • Ceramics / Materials
  • Radiomedicine / Medicine
  • Isotopes / Fission Reactors
  • Decommissioning / Fission Reactors
  • Particles, Fields and Accelerator Physics / Physics
  • Diagnostics & Devices / Medicine
  • Modelling and Risk Assessment / Environment
  • Atomic and Nuclear Physics / Physics
  • Materials and Materials Conversion / Fission Reactors
  • Composites / Materials
  • Data Storage and Peripherals / Information and Communications
  • Detection Devices / Instrumentation
  • Reactor Fuels and Fuel Engineering / Fission Reactors
  • Microbiology / Biotechnology
  • Space Safety / Space, Aircraft and Surface Transportation
  • Environmental Health and Safety / Environment
  • Experiments / Fission Reactors
  • Hybrid Systems and Fuel Cycle / Fusion
  • Astronomy / Space, Aircraft and Surface Transportation
  • Seismic Monitoring / Environment
  • Engineering Materials / Manufacturing Technology
  • Industrial Chemistry and Chemical Process Engineering / Chemistry
  • Other / Physics
  • High Performance Computing and Networking / Information and Communications
  • Other / Information and Communications
  • Photo and Radiation Chemistry / Chemistry
  • Miscellaneous Energy Conversion / Non-Nuclear Energy
  • Electrotechnology / Other
  • Materials / Fission Reactors
  • Radiobiology / Biotechnology
  • Organic and Electronics Materials / Materials
  • Microelectronics and Optoelectronics / Information and Communications
  • Software / Information and Communications
  • Other / Chemistry
  • Physical and Theoretical Chemistry / Chemistry
  • Remediation and Decontamination / Environment
  • Water Pollution and Control / Environment
  • Natural Resources and Earth Sciences / Other Basic Sciences
  • Disease Surveillance / Medicine
  • Cytology, Genetics and Molecular Biology / Biotechnology
  • Other / Fission Reactors
  • Fuel Conversion / Non-Nuclear Energy
  • Other / Medicine
  • Basic and Synthetic Chemistry / Chemistry
  • Air Pollution and Control / Environment

The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.

 

ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.

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