V. V. Bezlepkin

发表

Simulation of thermophysical processes with passive removal of residual heat of a VVER-640 reactor in design accidents with depressurization of the primary circuit

S. N. Volkova, Yu. A. Migrov, V. V. Bezlepkin, 2002 .

The device for core melt localization at the Tyan'van Nuclear Power Station with a VVER-1000 reactor

V. V. Bezlepkin, I. V. Kukhtevich, V. B. Khabenskii, 2001 .

ICONE11-36102 Core Catcher for Tianwan NPP with VVER-1000 reactor. Concept, Design and Justification

V. V. Bezlepkin, I. V. Kukhtevich, A. B. Nedorezov, 2003 .

Methodical specifics in substantiating passive safety systems for nuclear pwer stations with VVER-640 reactors

Yu. A. Migrov, V. V. Bezlepkin, I. V. Kukhtevich, 1996 .

The development of computer codes for the simulation of severe accidents at nuclear power stations I

Rafael V. Arutyunyan, V. V. Bezlepkin, A. V. Lukin, 2004 .

The concept of overcoming severe accidents at nuclear power stations with VVER reactors

V. V. Bezlepkin, I. V. Kukhtevich, S. V. Svetlov, 2004 .

Analyzing the possibility of retaining the corium in the vessel of a VVER-640 reactor in a severe accident with a damaged core

V. V. Bezlepkin, I. V. Kukhtevich, V. B. Khabenskii, 1996 .

Crucible-type core catcher for VVER-1000 reactor

V. V. Bezlepkin, I. V. Kukhtevich, Sevostian Bechta, 2005 .

Core melt stabilization concepts for existing and future LWRs and associated RaD needs

A. Miassoedov, V. V. Bezlepkin, Sevostian Bechta, 2015 .

The concept of localization of the corium melt in the ex-vessel stage of a severe accident at a nuclear power station with a VVER-1000 reactor

V. V. Bezlepkin, I. V. Kukhtevich, V. B. Khabenskii, 2001 .

Simulation of heat transfer processes in the containment shell of a nuclear power station with VVER reactors

V. V. Bezlepkin, P. L. Kirillov, V. V. Smirnov, 1995 .

Numerical Simulation of the Behavior of Fission Products in the Primary Circuit of the VVER During the LOCA Severe Accident

V. V. Bezlepkin, Valery F. Strizhov, A. E. Kiselev, 2009 .

Verification of the KUPOL-M code using the results of experiments

V. V. Bezlepkin, S. E. Semashko, A. D. Efanov, 2004 .

Development of a model for calculating the kinetics of aerosols in protective containments under emergency situations at nuclear power stations with VVER reactors

V. V. Bezlepkin, A. A. Ignat’ev, I. M. Ivkov, 2004 .

Analytical and experimental validation of the hydrogen mitigation system for the containment shell of a nuclear power station with a VVER-640 reactor

Yu. N. Shebeko, V. V. Bezlepkin, S. E. Semashko, 1995 .

The general concept of the safety of a nuclear power station with a VVER-640 reactor

V. V. Bezlepkin, M. A. Bykov, A. V. Molchanov, 1995 .

The concept of safety for accidents beyond the design basis at a nuclear power station with a VVER-640 reactor

V. V. Bezlepkin, V. K. Ivanov, V. S. Granovskii, 1995 .

Ensuring the hydrogen safety of an NPS with a VVER-1000 reactor

V. V. Smirnov, V. V. Bezlepkin, I. V. Kukhtevich, 2002 .

Influence of corium oxidation on fission product release from molten pool

D. Bottomley, Christophe Journeau, Luis E. Herranz, 2010 .

Verification of the BONUS module integrated into the SOCRAT code

V. V. Bezlepkin, Valery F. Strizhov, V. I. Tarasov, 2009 .

Development of choking models for computer thermohydraulic codes

V. V. Bezlepkin, V. Sidorov, S. Alekseev, 2010 .

Investigation of Heat Emission during Free Convection in Application to the Closure Relations for Computational Codes

V. V. Bezlepkin, A. A. Ignat’ev, M. Zatevakhin, 2014 .

Numerical Modeling of Steam-Gas Flow in NPP Containment with VVER and Passive Heat Removal

V. V. Bezlepkin, D. K. Zaitsev, E. Smirnov, 2014 .

Modeling processes in the melt localization facility for aes-2006 with vver-1200 during an unanticipated accident

V. V. Bezlepkin, V. Sidorov, O. Tokar, 2010 .

Computational-experimental modeling of processes in the protective shell with a passive condenser present in the passive heat-removal system

V. V. Bezlepkin, I. M. Ivkov, M. Zatevakhin, 2010 .

Modeling the dynamics of iodine in the protective shell during accidents in nuclear power plants with VVER

V. V. Bezlepkin, S. Semashko, L. Lebedev, 2010 .

Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site

V. V. Bezlepkin, M. A. Bol’shukhin, I. M. Ivkov, 2009 .

Computational and Experimental Validation of a Passive Heat Removal System for NPP Containment with VVER-1200

Yu. A. Migrov, V. V. Bezlepkin, V. K. Efimov, 2014 .

Experimental Study of a Containment Heat-Removal System on the SMK Stand

V. V. Bezlepkin, M. Zatevakhin, O. Krektunov, 2014 .

Experimental Study of a Containment Heat-Removal System on the SMK Stand

V. V. Bezlepkin, M. Zatevakhin, O. Krektunov, 2014, Atomic Energy.

Experimental studies of thermohydraulic processes for the passive heat-removal system at the Leningradskaya nuclear power plant

V. V. Bezlepkin, V. O. Kukhtevich, V. Sidorov, 2010 .

KMS Stand: Large-Scale Model of NPP Containment with VVER

Yu. A. Migrov, V. V. Bezlepkin, V. K. Efimov, 2014 .

Investigation of Heat Emission during Free Convection in Application to the Closure Relations for Computational Codes

V. V. Bezlepkin, A. A. Ignat’ev, M. Zatevakhin, 2014, Atomic Energy.

Investigation of aerosol kinetics in the protective envelope when analyzing accidental emissions at nuclear plants

V. V. Bezlepkin, I. M. Ivkov, M. Zatevakhin, 2010 .

Core Melt Stabilization Concepts for Existing and Future LWRs and Associated Research and Development Needs

V. V. Bezlepkin, Sevostian Bechta, Alexei Miassoedov, 2016 .