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#0064Concrete Protection of Reactors

Design of a nuclear reactor core melt catcher on the basis of zirconia concrete.

#0597Structure of Irradiated Materials

Fundamental Research of Materials Structure and Properties Changes Resulted from Irradiation by Means of Complex of Modern Physical Methods

#0797Safe Operation of VVER Reactor

Methodical Development for VVER Reactor Pressure Vessel State and Safe Operation Lifetime Evaluation by Fracture Mechanics Criteria

#0797.2Safe Operation of VVER Reactor

Methodical Development for WWER-1000 Reactor Pressure Vessel Safe Operation Lifetime Evaluation Allowing for Anticorrosive Cladding

#1950Phase Diagrams for Corium

Phase Diagrams for Multicomponent Systems Containing Corium and Products of its Interaction with NPP Materials (CORPHAD)

#1950.2Phase Diagrams for Corium

Phase Diagrams for Multicomponent Systems Containing Corium and Products of its Interaction with NPP Materials

#2048Improvement of Steels Corrosion Resistance

Improvement of Corrosion Resistance of Constructional Steels in Liquid Pb and Pb-Bi Alloys by Means of Their Surface Modification with the Help of Pulsed Electron Beams and Protective Coatings

#2680Minor Actinide Transmutation in Nitrides Fuel Environment

MATINE - Study of Minor Actinide Transmutation in Nitrides: Modelling and Measurements of Out-of-pile Properties

#2864Analytical Methods of Hydrogen and Helium Embrittlement

Development of Analytical Methods of Hydrogen and Helium Embrittlement of Nuclear Reactor Materials and Containers for Storage and Transport of Radioactive Materials

#3072Toughness Properties of Steels for Reactor Pressure Vessels

Modelling of Brittle and Ductile Fracture and Prediction of Irradiation Damage Effect on Fracture Toughness Properties of Steels for Reactor Pressure Vessels on the Basis of Local Approach

#3074.2Neutron Diffraction Study of Nuclear Reactor Materials

Neutron-Diffraction Study of Micro- and Macrostresses in Structural Ageing Alloys for Nuclear Power Engineering after Thermal and Radiation Exposure and Predicting Resistance to Radiation-Induced Swelling

#3420VVER-1000 Reactor Pressure Vessel

Material Science Work Package for Lifetime Extension of VVER-1000 Reactor Pressure Vessels (RPV) from High Nickel Materials

#3751Fission Product Yields

Complete Data Library on Nucleon-Induced Fission Product Yields for Applications in Wide Energy Region

#G-031Boron-11 Enriched Reactor Materials

Development and Creation of Reactor Materials Containing Isotope Modified Boron Enriched with Boron-11 Isotope.

#G-719Investigation of Destruction Mechanisms in Reactor Steels

Investigation of Destruction Mechanisms in Reactor Steels and Alloys under Cycling Deformation

#K-039Structural Materials Testing Complex

Development of Structural Materials Testing Complex Located at the Former Semipalatinsk Test-Site. Project SMTC-STS.

#K-1566Purification of Irradiated Beryllium

Recycling Technology of Irradiated Beryllium

#K-172Reactor Structural Material Degradation

Study of Structural Materials of the Nuclear Reactor WWR-K in View of its Recommissioning

#K-437Fast Reactor Materials Properties

Application of Structural Materials Data from the BN-350 Fast Reactor to Life Extension of Light Water Reactors

#K-812Fuel Assembly Materials under Dry Storage

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

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