Atomenergoproekt St Petersburg Research And Design Institute Spbaep

Saint Petersburg, Russia

Atomenergoproekt St Petersburg Research And Design Institute Spbaep

Saint Petersburg, Russia
SEARCH FILTERS
Time filter
Source Type

Ershov G.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Ermakovich Yu.L.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Kalinkin A.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Kalinkin A.I.,First Central Research Institute | Buharin B.Kh.,First Central Research Institute
Atomic Energy | Year: 2013

A critical analysis of the conventional models taking account of common-cause failures is presented. More accurate approaches to taking account of common-cause failures of equipment and systems in NPPs are proposed. © 2013 Springer Science+Business Media New York.


Fiskov A.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Makaseev A.Yu.,National Research Nuclear University MEPhI
Atomic Energy | Year: 2011

Methods of obtaining granular sorbents for catching and purifying volatile inorganic fluorides are examined. The results of optimizing the technology of granular lithium fluoride and approaches to obtaining pelleted barium and calcium fluorides are presented. The granules obtained gave capacity to 0.6 g HF/g sorbent while maintaining the initial structure. The initial destruction was negligible, the number of destroyed granules was the same after three sorption-desorption cycles. © 2011 Springer Science+Business Media, Inc.


Lebedev L.E.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Semashko S.E.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Frolov A.S.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep
Atomic Energy | Year: 2010

During a loss-of-coolant and core meltdown accident at a nuclear power plant fission products enter the atmosphere inside the protective shell. One of the main factors determining the effect on the environment, the dose loads in personnel and the general public in the first days after the accident is radioactive iodine. To evaluate the mass of the radioactive iodine entering the environment, it is necessary to calculate its concentration in the protective shell. The model developed to describe the dynamics of iodine and the computational module in the integrated code make it possible to perform numerical modeling of the behavior of iodine in the protective shell in the case of accidents at nuclear power plants with VVER reactors. The model makes it possible to take account of the effect of physicochemical processes on the formation of volatile forms of iodine as well as the dynamics of thermohydraulic parameters on the iodine distribution. Verification showed an adequate description of the dynamics of the volatile forms of iodine in the protective shell. © 2010 Springer Science+Business Media, Inc.


Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Sidorov V.G.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Astafieva V.O.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Tokar O.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep
Atomic Energy | Year: 2010

The results of a computational analysis of the behavior of melt in the facility used to localize melt for VVER-1200 (AES-2006 design), which were obtained using the GEFEST-ULR code, are presented. The main parameters of the melt are determined: the time variation of the component composition, the temperature and density of the oxide and metallic components and their relative arrangement. Using the KORSAR/GP thermohydraulic code, the minimum margin to crisis of heat transfer at the outer surface of the wall of the melt localization facility is analyzed. It is confirmed that heat transfer from the outer surface of the wall with normal operation of the cooling loop is reliable. © 2010 Springer Science+Business Media, Inc.


Alekseev S.B.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Svetlov S.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Sidorov V.G.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep
Atomic Energy | Year: 2010

The results of experimental investigation of choking in vertical tubes with diameter 20, 30, and 40 mm and 19-rod assembly with pressure 0.6-4.1 MPa in the absence of directed circulation of the coolant and with water level above the section under study are presented. Previously determined correlations for determining the counterflow of the phases during choking for a wide range of pressure and diameter of the sections are refined. The results of calculations, performed with the KORSAR and RELAP5/MOD3.2, of choking in experimental sections are presented. Comparative analysis has revealed discrepancies between the computations and the experimental data. It is concluded on the basis of the results obtained that the models of choking for the tested codes need additional work with a correction of relations for the flow rate of the phases. It is recommended that this be done using the correlations obtained in the course of the present experimental study. © 2010 Springer Science+Business Media, Inc.


Ivkov I.M.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Zatevakhin M.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Semashko S.E.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Ignatiev A.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep
Atomic Energy | Year: 2010

The course of an unanticipated accident with serious damage to the core is characterized by the emission of a large quantity of radioactive materials into the first loop and then into the space inside the protective shell. The majority of the fission products enter the protective shell in the form of radioactive aerosols, whose leakage largely determines the consequences of a serious accident. This makes it necessary to model the dynamics of multicomponent aerosols taking account of the coagulation, change of their composition and mass as a result of the condensation-evaporation and dissolution of the gaseous components as well as the precipitation of the particles on different surfaces. A program for calculating the aerosol kinetic during the course of a serious accident is examined. © 2010 Springer Science+Business Media, Inc.


Kukhtevich V.O.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Svetlov S.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Sidorov V.G.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | And 5 more authors.
Atomic Energy | Year: 2010

The results of experimental studies of a passive system for removing heat through steam generators which were performed on a large-scale (1/110) stand at the Scientific-Industrial Association for Research and Design of Power-Generation Equipment (NPO TsKTI, St. Petersburg) are presented. The experiments show that the system performs reliably and effectively as designed. The experimental data were used to verify the thermohydraulic codes KORSAR and SOKRAT, which are used to model the thermohydraulic processes in the system at the Leningradskaya nuclear power plant. © 2010 Springer Science+Business Media, Inc.


Semashko S.E.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Bezlepkin V.V.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Zatevakhin M.A.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Simakova O.I.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep | Ivkov I.M.,Atomenergoproekt St Petersburg Research And Design Institute Spbaep
Atomic Energy | Year: 2010

The modeling of the operation of a passive condenser based on a numerical solution of three-dimensional equations of hydrodynamics is examined. Questions associated with correct modeling of turbulent transport under free-convection conditions are examined. A model taking account of the dynamics of a condensate film and the conditions of heat and mass transfer on its surface is proposed for surface condensation. The results are used to develop recommendations for closure relations used in point codes with whose help design validation of a passive system removing heat from beneath the protective shell is performed. © 2010 Springer Science+Business Media, Inc.

Loading Atomenergoproekt St Petersburg Research And Design Institute Spbaep collaborators
Loading Atomenergoproekt St Petersburg Research And Design Institute Spbaep collaborators