safety analysis

Development of the integrated model of MBIR research reactor facility in the simintech simulation environment using the PRISET estimate code

12/25/2016 2016 - #04 Modelling processes at nuclear facilities

Parshikov I.A. Dolgov Yu.A. Larionov I.A. Shchekaturov A.M.

Accident analysis of reactor facility by using thermal hydraulic code KORSAR

7/14/2014 2014 - #02 Global safety, reliability and diagnostics of nuclear power installations

Parshikov I.A. Soloviev D.S. Solovyev S.V.