Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2

System of models and codes for substantiating the safety of radiochemical technologies: a review

Molten salt reactor for curium transmutation

Calculation of a gas centrifuge cascade with loss of working substance in stages

System of fuel cladding failure detection for the BREST-OD-300 reactor plant

DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants

Study of the coolant flow rate through the fuel assemblies of the IVV-2M reactor core. Part 2

System of models and codes for substantiating the safety of radiochemical technologies: a review

Molten salt reactor for curium transmutation

Calculation of a gas centrifuge cascade with loss of working substance in stages

System of fuel cladding failure detection for the BREST-OD-300 reactor plant

DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants