BREST

Experience of Using BN-600 Reactor Core for Experimental Irradiation

9/10/2025 2025 - #03 Nuclear materials

Belov S.B. Vasilyev B.A. Radionycheva A.A. Farakshin M.R. Tuchkov A.M.

Features of Methods for Monitoring the Tightness of the Cladding of Fuel Elements in Fast Breeder Reactors with Lead Coolant

9/23/2021 2021 - #03 Global safety, reliability and diagnostics of nuclear power installations

Dragunova A.V. Morkin M.S. Perevezentsev V.V.