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Member Countries

European Commission / Joint Research Center / Institute for Transuranium Elements

General information

Full Name
European Commission / Joint Research Center / Institute for Transuranium Elements (ITU)


Address
PO Box 2340, D-76125, Karlsruhe, Germany


Phone
49+7247+951386


Email
roland.schenkel@jrc.org;


WWW
itumagill.fzk.de;


ISTC Projects

  • 0272 - Minor-Actinide Burning in Fast Reactors
  • 0273 - Radiation Characteristics of MOX Fuel
  • 0279 - Extraction of Fission Products from Irradiated Fuel
  • 0290 - Plutonium Utilization in Nuclear Reactors
  • 0330 - Reprocessing of Pu-Contaminated Water
  • 0348 - Radioactive and Fissionable Materials Detection
  • 0371 - Pu-Utilization in LWR Experiments
  • 0534 - Uranium Dioxide Properties
  • 0534.2 - Uranium Dioxide Properties
  • 0696 - Patent Information on Nuclear Reactors
  • 0723-2 - Recycling Weapon-grade U and Pu in U-Th Closed-cycle Reactors
  • 0771 - MOX Fuel Fabrication
  • 0833 - Corium Interaction with Reactor Vessel
  • 0833.2 - Corium Interaction with Reactor Vessel
  • 1193 - Fuel Materials with Non-Uranium Diluent
  • 1450 - Radiopharmaceuticals for Diagnostics
  • 1644 - Nuclear Materials Identification
  • 1648.2 - Post-Crash Fuel Reflood
  • 1950.2 - Phase Diagrams for Corium
  • 2391 - Carbon Materials for Nuclear Waste Storage and Transmutation
  • 2585 - Characterization of Samples with Spontaneously Fissioning Isotopes
  • 2916 - Nuclear Fuel Behavior During Chernobyl Accident
  • 2936 - Reactor Core Melting
  • 3194 - Fuel Assembly Under Severe Accident Conditions
  • 3217 - Plutonium, Neptunium and Uranium Trace Amounts
  • 3261 - Curium in molten chlorides
  • 3345 - Ex-Vessel Source Term ANalysis (EVAN)
  • 3453 - Eddy Current Inspection of Reactor Case Details
  • 3592 - Corium Melt Interaction with Reactor Vessel Steel
  • 3608 - Minor Actinide Transmutation in Inert Matrices Fuels
  • 3635 - VVER Vessel in Severe Accident
  • 3690 - Fuel Assemblies under Severe Accident
  • 3702 - Long-term Behavior of Corium after Accident
  • 3749 - Molten Salt Applications for Nuclear Energy
  • 3813 - Phase Relations in Corium Systems
  • 3831 - Heating and Retention of Corium
  • 3876 - Thermo-Hydraulics of Oxidising Melt in Severe Accidents
  • 3919 - Fission Products Release from Heated Fuel
  • 3928 - Control of Fissile Materials in Gas Clearing and Pipelines
  • 3936 - Fuel Assemblies under Severe Accident Conditions
  • 3957 - Counteraction against Illicit Trafficking of Nuclear Materials
  • A-1837 - Safety and Integrity of Nuclear Fuel
  • K-1797 - Fuel for High Temperature Gas Cooled Reactor
  • K-672 - New Tritium Detection Technology
  • K-749 - "Hot" Radioactive Particles

Tech areas

  • Fuel Cycle / Fission Reactors
  • Reactor Fuels and Fuel Engineering / Fission Reactors
  • Radioactive Waste Treatment / Environment
  • Detection Devices / Instrumentation
  • Nuclear and Other Technical Data / Fission Reactors
  • Reactor Concept / Fission Reactors
  • Nuclear Safety and Safeguarding / Fission Reactors
  • Isotopes / Fission Reactors
  • Sensors and Signal Processing / Information and Communications
  • Software / Information and Communications
  • Monitoring and Instrumentation / Environment
  • Materials and Materials Conversion / Fission Reactors
  • Modelling / Fission Reactors
  • Photo and Radiation Chemistry / Chemistry
  • Materials Synthesis and Processing / Materials
  • Atomic and Nuclear Physics / Physics
  • Nuclear Instrumentation / Fission Reactors
  • Solid Waste Pollution and Control / Environment
  • Materials / Fission Reactors
  • Reactor Engineering and NPP / Fission Reactors
  • Experiments / Fission Reactors
  • Modelling and Risk Assessment / Environment
  • Structural Mechanics / Physics
  • Decommissioning / Fission Reactors
  • Safety and Security / Chemistry
  • Dangerous Materials Transportation / Environment
  • Control and Accounting / Fission Reactors
  • Biochemistry / Biotechnology
  • Remediation and Decontamination / 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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