5 results on '"Ioannisian, M. V."'
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2. KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors
3. Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility
4. Benchmark Experiments for Verification of Nuclear Data Libraries for Designing Fusion Blankets
5. Radiation and Nuclear Physics Aspects of the Use of the Thorium Fuel Cycle in a Hybrid Fusion Facility
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