reactor cooldown

Experience with Using the Coupled 1D-3D Thermal-Hydraulic Analysis to Simulate an Emergency Cooldown of a Sodium-Cooled Fast Reactor

9/17/2026 2026 - #03 Thermal physics and thermal hydraulics

Didenko D.V. Anfimov A.M. Nikanorov O.L. Rogozhkin S.A. Timin D.A. Fadeev I.D. Aksenov A.A. Zhestkov M.N. Kashirin V.S. Sazonova M.L. Sinitsyn A.V. Yushchenko A.A.

Development of a Methodological Approach for Analytical Study of the Coolant Flow in the Process of Sodium-Cooled Reactor Cooldown

11/19/2020 2020 - #04 Thermal physics and thermal hydraulics

Didenko D.V. Baluyev D.E. Nikanorov O.L. Rogozhkin S.A. Shepelev S.F. Aksenov A.A. Zhestkov M.N. Shchelyaev A.E.