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#K-1006Off-Gas Purification System for BN-350 Reactor Sodium Processing Facility

Upgrade of the Off-Gas System for the BN-350 Reactor Sodium Coolant Processing Facility

#K-2406Remediation of in-situ leaching uranium mines

Investigation of possibilities of remediation of spent uranium deposits on the basis of the technological scheme in-situ leaching

#K-437Fast Reactor Materials Properties

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

#K-437.2Fast Reactor Materials Properties

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

#K-512Cesium Trap for BN-350 Reactor

Develop, Install, and Operate a Cesium Trap, Based on the U.S. Technologies, to Reduce Cesium Levels in the BN-350 Primary Sodium and Enhance Plant Fire Protection Capabilities to Support Cesium Trap Operation

#K-513BN-350 Reactor Decommissioning Concept

Preparation of a Decommissioning Plan for International Review to Place the BN-350 Reactor in a SAFESTOR Condition

#K-883Corrosion Resistance of Radwaste Storage

Corrosion Protection Experimental Studies and Tests under Gamma-Radiation and Heating Combined Effect in BN-350 Spent Fuel Dry Long-Term Storage Facility Silo Models

#K-969Scaled-Down Simulation of BN-350 Sodium Coolant Processing Facility

Design and Development of a Scaled-Down Simulation Complex of Automated Control and Dataware System for BN-350 Sodium Coolant Processing Workflow

#K-970Development of Technology of Sodium Hydroxide Processing into Geocement Stone

Development of Experimental-Industrial Technology of Radioactive Waste Processing into Geocement Stone and Equipment for its Realization