25 Result(s)

Article

Investigation of the Heat-Insulation Properties of the Steam-Water Gap in the Downcomer Pipes of a Steam Generator

The results of an experimental investigation of heat transfer through a gap filled with a steam–water mixture are presented. It is shown that heat transfer through such a gap is considerably different from hea...

A. A. Semchenkov, O. Yu. Novosel’skii, Yu. V. Lemekhov, A. G. Khizhnyak… in Atomic Energy (2014)

Article

Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code

The characteristics the flow of water in the hydraulic path of the multipurpose valve with the parameters of coolant had at the moment when the accident began in Unit 4 at the Chernobyl nuclear power station a...

O. Yu. Novosel’skii, A. P. Skibin, S. L. Solov’ev, A. V. Shishov in Thermal Engineering (2007)

Article

The application of computational fluid dynamics for determining the hydraulic characteristics of pipelines at nuclear power stations

The application of computational fluid dynamics for calculating the hydraulic resistances of elements of the pipeline system for steam and gas discharges at a nuclear power station equipped with an RBMK-1000 r...

O. Yu. Novosel’skii, V. E. Petrov, A. P. Skibin, S. L. Solov’ev… in Thermal Engineering (2006)

Article

Increasing the nominal safety of the no. 5 unit of the Kursk nuclear power plant

The main technical measures for increasing the nominal safety of the No. 5 unit of the Kursk nuclear power plant are presented: optimization of the neutron-physical characteristics of the core, adoption of a c...

A. A. Potapov, V. M. Panin, S. G. Ukharov, O. Yu. Novosel’skii in Atomic Energy (2006)

Article

Investigation of the development of the 1986 accident at the Chernobyl nuclear power plant

Important results obtained from investigations of the diverse processes that occurred during the accident in the No. 4 unit of the Chernobyl nuclear power plant on April 26, 1986 are presented in a concise for...

Yu. M. Cherkashov, O. Yu. Novosel’skii, K. P. Checherov in Atomic Energy (2006)

Article

Comprehensive Analysis of Mechanical and Thermohydraulic Processes in the Graphite Masonry of Channel Rectors during an Accidental Rupture of a Fuel Channel

A methodology and preliminary results of a computational analysis of the processes occurring in the graphite masonry in RBMK channel reactors during the rupture of a fuel channel as a result of accidental over...

S. L. Solov'ev, B. A. Gabaraev, O. Yu. Novosel'skii, V. N. Filinov… in Atomic Energy (2003)

Article

Assessment of the Vulnerability of RBMK Fuel Channels to Loads Produced by the Rupturing of One Channel

The possibilities for a fuel-channel pipe in RBMK, with nominal parameters, to rupture under internal and external loading caused by the rupture of a neighboring damaged channel, which becomes overheated for a...

B. A. Gabaraev, O. Yu. Novosel'skii, V. N. Filinov, L. M. Parafilo in Atomic Energy (2000)

Article

Criteria for the fracture of RBMK fuel-channel tubes when accidental overheating occurs

O. Yu. Novosel'skii, V. N. Filinov in Atomic Energy (1997)

Article

Investigation of the behavior of the technological channels of a RBMK reactor under conditions of heating during an accident

O. Yu. Novosel'skii, V. N. Filinov, I. I. Kryuchkov in Atomic Energy (1995)

Article

Investigation of the hydraulic characteristics of the water-leveling pipes of RBMK-1000 separator drums

V. I. Esikov, V. B. Karasev, O. Yu. Novosel’skii, V. N. Smolin… in Atomic Energy (1994)

Article

Methodological questions concerning investigations of the hydraulic characteristics of the water-leveling pipes of the separator drums in a RBMK reactor

V. B. Karasev, O. Yu. Novosel’skii, V. N. Smolin, A. V. Shishov in Atomic Energy (1994)

Article

Separation system of a new-generation boiling-water vessel reactor

V. B. Karasev, O. Yu. Novosel’skii, A. V. Shishov in Atomic Energy (1994)

Article

Effect of nonsimultaneous rupture of the technological channels on the dynamics of pressure in the reactor space of a RBMK unit

B. A. Gabaraev, O. Yu. Novosel'skii, V. K. Safonov, S. L. Simonov in Atomic Energy (1993)

Article

Testing the VSPLESK program with data of experiments made on a model of an accident localization system

V. B. Karasev, O. Yu. Novosel'skii, V. K. Safonov, A. N. Murashko… in Atomic Energy (1993)

Article

Steam-separator modernization as a way to improve RBMK-1000 safety

R. V. Vasil'eva, V. M. Eshcherkin, Yu. A. Letnitskii, V. B. Karasev… in Atomic Energy (1992)

Article

Flow-rate characteristics of laval nozzles with different transverse-injection methods

1. Transverse-injection methods significantly reduce the critical flow rate of slightly underheated and saturate...

B. A. Gabaraev, É. K. Karasev, O. Yu. Novosel'skii, S. Z. Lutovinov… in Atomic Energy (1992)

Article

Pressure behavior in the RBMK reator space

B. A. Gabaraev, Yu. V. Mironov, O. Yu. Novosel'skii, S. L. Simonov… in Soviet Atomic Energy (1990)

Article

Separating drum testing at the Ignalin RBMK-1500 main unit

O. Yu. Novosel'skii, V. B. Karasev, E. V. Sakovich, V. K. Safonov… in Soviet Atomic Energy (1989)

Article

Study of the flow rate characteristics of Laval nozzles with transverse injection through an opening in the side wall

1. It was found that the effectiveness of transverse injection as a method for reducing the critical discharge i...

B. A. Gabaraev, É. K. Karasev, S. Z. Lutovinov, O. Yu. Novosel'skii… in Soviet Atomic Energy (1989)

Article

Discharge of boiling water and steam-water mixture through a convergent nozzle

B. A. Gabaraev, É. K. Karasev, S. Z. Lutovinov, O. Yu. Novosel'skii… in Soviet Atomic Energy (1989)