Mikhin Stepan A.

Post-graduate student

IATE MEPhI

mikhinsa@oiate.ru

On the Possibility of Cooling the High-Power VVER Reactor Pressure Vessel Using an Air-Droplet Spray in the Event of a Beyond Design Basis Accident

3/25/2025 2025 - #01 Global safety, reliability and diagnostics of nuclear power installations

Zaryugin D.G. Leskin S.T. Mikhin S.A. Sergeev V.V. Slobodchuk V.I.

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.