Novovoronezh, Russia
Novovoronezh, Russia

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Ivanov E.A.,RAS Institute for Nuclear Research | Pyrkov I.V.,RAS Institute for Nuclear Research | Smirnov S.E.,Novovoronezh Nuclear Power Plant | Smirnov D.S.,Novovoronezh Nuclear Power Plant | And 4 more authors.
Atomic Energy | Year: 2015

The technical requirements of a system that continually monitors the condition of the safety barriers of nuclear power plants are substantiated. It is shown for the example of the Rostov NPP that power units with VVER which are operating, under construction, or in the design stage can be equipped with a measuring system for monitoring radiation leaks from the steam generators. This improves safety (by not allowing emergency situations) and increases the installed capacity utilization factor (by eliminating unjustified shutdowns of power units) of operating power plants. © 2015 Springer Science+Business Media New York


Tomarov G.V.,Geotherm EM | Povarov V.P.,Novovoronezh Nuclear Power Plant | Shipkov A.A.,Geotherm EM | Gromov A.F.,Novovoronezh Nuclear Power Plant | And 2 more authors.
Thermal Engineering (English translation of Teploenergetika) | Year: 2015

Matters concerned with making efficient use of the information–analytical system on the flow- accelerated corrosion problem in setting up in-service examination of the metal of pipeline elements operating in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh NPP are considered. The principles used to select samples of pipeline elements in planning ultrasonic thickness measurements for timely revealing metal thinning due to flow-accelerated corrosion along with reducing the total amount of measurements in the condensate-feedwater path are discussed. © Pleiades Publishing, Inc., 2015.


Tomarov G.V.,Geotherm EM | Povarov V.P.,Novovoronezh Nuclear Power Plant | Shipkov A.A.,Geotherm EM | Gromov A.F.,Novovoronezh Nuclear Power Plant | And 3 more authors.
Thermal Engineering (English translation of Teploenergetika) | Year: 2015

Specific features relating to development of the information-analytical system on the problem of flow-accelerated corrosion of pipeline elements in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh nuclear power plant are considered. The results from a statistical analysis of data on the quantity, location, and operating conditions of the elements and preinserted segments of pipelines used in the condensate-feedwater and wet steam paths are presented. The principles of preparing and using the information-analytical system for determining the lifetime to reaching inadmissible wall thinning in elements of pipelines used in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh NPP are considered. © 2015, Pleiades Publishing, Inc.


Kazakov V.A.,RAS Institute for Nuclear Research | Zhudenkov V.V.,RAS Institute for Nuclear Research | Kazakov K.V.,RAS Institute for Nuclear Research | Povarov V.P.,Novovoronezh Nuclear Power Plant | Vitkovskii I.L.,Novovoronezh Nuclear Power Plant
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

Ensuring transient stability of nuclear power plant units in transient modes of their operation is one of the goals aimed at achieving enhanced safety and reliability of nuclear power plants. Field experience shows that for nuclear power plants equipped with VVER-1000 reactors, matters relating to transient stability in modes involving disconnection of the power unit main equipment, such as reactor coolant pumps, turbine-driven feedwater pumps, and turbine generator, are of most concern. Specialists of the Institute for Nuclear Power Plant Research perform comprehensive investigations of the technological processes aimed at working out measures for achieving better transient stability of nuclear power plant units. The article presents the results of joint activities carried out by specialists of the Institute for Nuclear Power Plant Research and the Novovoronezh nuclear power plant on enhancing the transient stability of Unit 5 at the Novovoronezh nuclear power plant. © 2014 Pleiades Publishing, Inc.


Proskuryakov K.N.,Moscow Power Engineering Institute | Fedorov A.I.,Novovoronezh Nuclear Power Plant | Zaporozhets M.V.,Moscow Power Engineering Institute
Thermal Engineering (English translation of Teploenergetika) | Year: 2015

The accident at the Japanese Fukushima Daiichi nuclear power plant (NPP) caused by an earth- quake showed the need of taking further efforts aimed at improving the design and engineering solutions for ensuring seismic resistance of NPPs with due regard to mutual influence of the dynamic processes occurring in the NPP building structures and process systems. Resonance interaction between the vibrations of NPP equipment and coolant pressure pulsations leads to an abnormal growth of dynamic stresses in structural materials, accelerated exhaustion of equipment service life, and increased number of sudden equipment failures. The article presents the results from a combined calculation-theoretical and experimental substantiation of mutual amplification of two kinds of external periodic loads caused by rotation of the reactor coolant pump (RCP) rotor and an earthquake. The data of vibration measurements at an NPP are presented, which confirm the predicted multiple amplification of vibrations in the steam generator and RCP at a certain combination of coolant thermal-hydraulic parameters. It is shown that the vibration frequencies of the main equipment may fall in the frequency band corresponding to the maximal values in the envelope response spectra constructed on the basis of floor accelerograms. The article presents the results from prediction of conditions under which vibroacoustic resonances with external periodic loads take place, which confirm the occurrence of additional earthquake-induced multiple growth of pressure pulsation intensity in the steam generator at the 8.3 Hz frequency and additional multiple growth of vibrations of the RCP and the steam generator cold header at the 16.6 Hz frequency. It is shown that at the elastic wave frequency equal to 8.3 Hz in the coolant, resonance occurs with the frequency of forced vibrations caused by the rotation of the RCP rotor. A conclusion is drawn about the possibility of exceeding the design level of equipment vibrations under the effect of external periodic loads caused by an earthquake when the vibration frequency of the reactor plant main equipment and the frequency of elastic waves fall in the frequency band corresponding to the maximal values of envelope response spectra. © 2015, Maik Nauka-Interperiodica Publishing, all rights reserved.


Bakirov M.B.,Scientific Certification Training Center for Materials Science and Nuclear Equipment Components Service Life Materials Science and Service Life Center | Levchuk V.I.,Scientific Certification Training Center for Materials Science and Nuclear Equipment Components Service Life Materials Science and Service Life Center | Povarov V.P.,Novovoronezh Nuclear Power Plant | Gromov A.F.,Novovoronezh Nuclear Power Plant
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

Inadmissible operational flaws occurring in the critical zones of heat-transfer and mechanical equipment are commonly revealed in all nuclear power plant units both in Russia and abroad. The number of such flaws will only grow in the future because the majority of nuclear power plants have been in operation for a time that is either close to or even exceeds the assigned service life. In this connection, establishing cause-and-effect relations with regard to accelerated incipience and growth of flaws, working out compensating measures aimed at reducing operational damageability, and setting up monitoring of equipment integrity degradation of during operation are becoming the matters of utmost importance. There is a need to introduce new approaches to comprehensive diagnostics of the technical state of important nuclear power plant equipment, including continuous monitoring of its operational damageability and the extent of its loading in the most critical zones. Starting from 2011, such a monitoring system has successfully been used for the Novovoronezh NPP Unit 5 in the zone of weld joint no. 111-1 of steam generator no. 4. Based on the results from operation of this system in 2011–2013, unsteady thermally induced force effects (periodic thermal shocks and temperature abnormalities) were reveled, which had not been considered in the design, and which have an essential influence on the operational loading of this part. Based on an analysis of cause-and-effect relations pertinent to temperature abnormalities connected with technological operations, a set of measures aimed at reducing the thermally induced force loads exerted on pipeline sections was developed, which includes corrections to the process regulations for safe operation and to the operating manuals (involving changes in the algorithms for manipulating with the stop and control valves in the steam generator blowdown system). © Pleiades Publishing, Inc., 2014.


The No. 5 unit of the Novovoronezh nuclear power plant, starting commercial operations on September 26, 1980, is the first power-generating unit with a 1000 MW VVER in our country. The assimilation of its power gave invaluable experience to designers, builders, and equipment manufacturers; this experience was taken into account in the design solutions for next-generation power-generating units. A large volume of work on increasing the efficiency, reliability, and safety was performed over a 30-year service life. At present, the power-generating unit has been shut down for a major overhaul for upgrading according a program for extending the service life by 25-30 years. © 2011 Springer Science+Business Media, Inc.


Povarov V.P.,Novovoronezh Nuclear Power Plant.
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika | Year: 2015

Reliability of planned and exploiting complex technical objects, such as AES-main condition of safety for the man and the environment. The basic factors, which influence reliability are:-absence of errors in design and calculation of constructions, the correctness of the selection of materials and technology of production;-quality of the materials used;-quality of assembly and welding works;-operating condition and operational control. Despite the fact that with the design and the operation AES, clout is given to the guarantee of reliability, operating experience showed that in the welded joint of No111 PGV-1000M is possible crack formation. The mechanism of origin and increase in the cracks, until now, is not unambiguously determined. In the article are represented the results of investigating the reasons for the damage of metal in the zone of the welded joint of No of 111 weldings of hot collector to the branch pipe Of du1200 of housing. The first case of the splitting of metal in the region of the connection of collector with the housing PG occurred in 1998 on 5 block Novovoronezh atomic station. Subsequently are discovered uniform damages even on several PG, which made it necessary to consider the cases of damage as the system problem, which has the general reasons. To identify factors that lead to cracking, conducted a significant amount of R & d: analysis of the manufacture and properties of the metal; a detailed computational study of the stress state from operational factors; assessment of residual stresses from manufacturing techniques; experimental study of the stress state of the node models and the NPP; measurements and the analysis of the displacements of equipment RU with the thermal expansion; the determination of the critical dimension of cracks; the correction working of the working medium of secondary circuit; the exception of the thermo-shocks, connected with the work of the system of scavenging.

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