sodium coolant

Computational Analysis of Large Water-to-Sodium Leak Incident in the BN-600 Steam Generator

6/05/2024 2024 - #02 Global safety, reliability and diagnostics of nuclear power installations

Perevoznikov S.V. Mikhin S.A. Kamaev A.A. Pazin G.N. Mirzeabasov O.A. Myazdrikova O.I. Borisov V.V. Pakhomov I.A.

Principles of Construction and Development of an Automatic Protection System for Steam Generators of Fast Reactors

9/25/2023 2023 - #03 Current issues in nuclear energy

Borisov V.V. Kamaev A.A. Myazdrikova O.I. Mikhin S.A. Pakhomov I.A. Perevoznikov S.V.

Key Technical Solutions for the BN-350 Power Unit That Have Influenced the BN Reactor Design Evolution

9/25/2023 2023 - #03 Letters ti the editorial office

Kamaev A.A.

Conceptual issues of cold filter-traps development for sodium coolant purification in fast reactors

3/19/2020 2020 - #01 Chemistry, physics and technology of reactor coolants

Alekseev V.V. Kuzina Yu.A. Sorokin A.P.

Development and verification of the TR-BN program for validation of the normal operation modes in the BN reactors

3/28/2016 2016 - #01 Modelling processes at nuclear facilities

Fadeev I.D. Dmitrieva I.V. Osipov S.L. Rogozhkin S.A.