The Experts below are selected from a list of 4566 Experts worldwide ranked by ideXlab platform
V F Tyapkov - One of the best experts on this subject based on the ideXlab platform.
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water chemistry in Power units at Nuclear Power Stations equipped with rbmk 1000 reactors
Thermal Engineering, 2011Co-Authors: V F Tyapkov, Yu I Chudakova, O A AlekseenkoAbstract:The modified standards for the water chemistry at Nuclear Power Stations equipped with RBMK-1000 reactors for the entire service life of Power units are presented. Stages through which the information-analytical system Center for Providing Chemical Support to Nuclear Power Stations was established and developed and its current structure are described. An example of analyzing the water chemistry of coolant used in the multiple forced circulation loop and operational data obtained through the communication channels with the above-mentioned system is given, and the main objectives pursued by the Center for Providing Chemical Support to Nuclear Power Stations equipped with RBMK reactors are described in the part of conducting their water chemistry and using means and systems for maintaining water chemistry parameters.
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a comprehensive approach to selecting the water chemistry of the secondary coolant circuit in the projects of Nuclear Power Stations equipped with vver 1200 reactors
Thermal Engineering, 2011Co-Authors: V F TyapkovAbstract:The paper presents the results obtained from studies on selecting the water chemistry of the secondary coolant circuit carried out for the project of a Nuclear Power station equipped with a new-generation VVER-1200 reactor on the basis of case calculations and an analysis of field experience gained at operating Nuclear Power Stations.
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problems connected with polishing turbine condensate of Power units at Nuclear Power Stations equipped with vver reactors and ways of improving its quality
Thermal Engineering, 2010Co-Authors: V F TyapkovAbstract:Experience gained from operation of the turbine condensate polishing system used at existing Nuclear Power Stations equipped with VVER reactors is analyzed. The optimal scheme of polishing turbine condensate intended for use at newly designed Nuclear Power Stations is substantiated.
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introduction of water chemistry conditions of the secondary coolant circuit with metering organic amines at Nuclear Power Stations equipped with vver 1000 reactors
Thermal Engineering, 2009Co-Authors: V F Tyapkov, S F Erpyleva, V V BykovaAbstract:Results from introduction of new water chemistry conditions involving metering of organic amines (morpholine and ethanolamine) at Nuclear Power Stations equipped with VVER-1000 reactors are presented.
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the introduction of precoat ion exchange filtration in special water treatment plants at operating rbmk 1000 reactor based Nuclear Power Stations
Thermal Engineering, 2005Co-Authors: V F Tyapkov, Yu I Chudakova, V M Tishkov, O V YatskoAbstract:We describe the experience gained from commercial introduction of precoat ion-exchange filtration in water-treatment plants at operating Nuclear Power Stations. The list of factory-standard powdered ion-exchange resins is presented, and their physicochemical properties are given. The possibility is shown of improving, through the use of precoat ion-exchange filtration, the water chemistry conditions at either newly designed or already operating Nuclear Power Stations.
S I Brykov - One of the best experts on this subject based on the ideXlab platform.
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substantiation of recommendations for ensuring the design service life of heat transfer tubes used in a pgv 1000mkp steam generator
Thermal Engineering, 2011Co-Authors: V S Popadchuk, N B Trunov, S I Brykov, Yu R Zhukov, R A Tupikov, A V Seleznev, R I Popkov, M S Metalnikov, P S Styazhkin, G P KarzovAbstract:We present the results obtained from tests and studies carried out on the model of tube bundles for a PGV-1000 horizontal steam generator that were conducted for experimentally substantiating the design service life of a steam generator tube bundle intended for use at new Nuclear Power Stations equipped with a PGV-1000MKP steam generator. Measures taken to minimize the incipience and development of local corrosion damage to the heat-transfer tubes and ensure their design service life are substantiated and confirmed.
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the capacities of a corrosion fatigue monitoring system in managing the service life of steam generators operating at Nuclear Power Stations equipped with a vver 1000m reactor
Thermal Engineering, 2007Co-Authors: G F Banyuk, S I Brykov, O P Arkhipov, V G Kritskii, Yu V Kharitonov, I G Berezina, M V SofinAbstract:We consider the possibilities of using a corrosion-fatigue monitoring system for operatively monitoring the corrosion of heat-transfer tubes in steam generators operating at Nuclear Power Stations equipped with VVER reactors. It is proposed that this system be tested on a Power unit built around a VVER-1000 reactor.
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improvement of the technology of chemical washing of steam generators at Nuclear Power Stations with vver reactors
Thermal Engineering, 2001Co-Authors: O P Arkhipov, S I Brykov, L A Siryapina, A A Efimov, B A Gusev, V V Krivobokov, A K AndrianovAbstract:The results of a comparison of the standard prescription for washing solutions on the basis of ethylenediaminetetraacetic acid (EDTA) and a new prescription on the basis of EDTA and ammonium acetate (NH 4 Ac) for the chemical washing of steam generators at Nuclear Power Stations (NPS) with VVER- 1000 reactors from iron oxide copper-containing deposits are discussed. The data obtained indicate that the latter solution is more effective when washing out oxide and metallic copper.
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experience with chemical washing of steam generators in the course of scheduled maintenance at Nuclear Power Stations with vver 1000 reactors
Thermal Engineering, 1999Co-Authors: S I Brykov, O P Arkhipov, L A Siryapina, V A MametAbstract:The effect of the deposits on heat-transfer tubes on their corrosive damage is discussed. The procedure and results of chemical washing of steam generators carried out in the course of scheduled maintenance (SM) at Nuclear Power Stations (NPS) with VVER-1000 reactors are described.
A. A. Shipkov - One of the best experts on this subject based on the ideXlab platform.
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Results from additional field examination of pipelines carried out at Russian Nuclear Power Stations in accordance with the Mihama program
Thermal Engineering, 2011Co-Authors: V. N. Lovchev, D. F. Gutsev, G. V. Tomarov, A. A. Shipkov, N. S. KoreshkovaAbstract:The results of additional field examination of pipelines obtained in the course of carrying out corrective measures at Russian Nuclear Power Stations in connection with the event that occurred at the Mihama Nuclear Power station are analyzed. The role of these data and the possibility of using them in current and future works carried out by the OAO Rosenergoatom Concern on the problem relating to erosion-corrosion of the metal used in Power units at Nuclear Power Stations are shown.
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principles of development and specific features relating to practical application of software for solving problems connected with erosion corrosion of metal in Power engineering
Thermal Engineering, 2011Co-Authors: G. V. Tomarov, A. A. ShipkovAbstract:Principles used in the development of modern computation codes for calculating erosion-corrosion of Power equipment are considered. Specific features of their practical applications aimed at preventing, revealing, and eliminating erosion-corrosion thinning of the metal of elements used in the units of Power Stations are analyzed. Results obtained from using the domestically developed computation code RAMEK for operating Power units are presented and prospects for implementing it in designing new Power units of Nuclear Power Stations are determined.
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Calculated and experimental substantiation of operating conditions under which adequate erosion resistance of valves used in Power units at Nuclear Power Stations is ensured
Thermal Engineering, 2010Co-Authors: G. V. Tomarov, A. A. Shipkov, N. S. KoreshkovaAbstract:A procedure for revealing factors causing damage to metal and the dominating mechanism through which this damage occurs that was developed earlier is applied for substantiating the operating conditions of valves with D _nom = 800 mm installed in the multiple forced circulation loop of Power units at Nuclear Power Stations equipped with RBMK-1000 reactors under which their resistance to erosion is ensured. Operating conditions under which cavitation erosion may occur are established, and practical proposals on how to prevent damage to the metal of a throttle-control valve’s body are presented.
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operative management of activities on monitoring the erosion corrosion state of elements used in the condensate feedwater path of a Nuclear Power station
Thermal Engineering, 2010Co-Authors: G. V. Tomarov, A V Shutikov, A. A. Shipkov, A I Usanov, Yu M Kanyshev, A V Zelenin, V A Gilev, S V Yakushev, B L Podvolotskii, N. S. KoreshkovaAbstract:New principles, methods, and measures used for preventing the occurrence of failures in elements, pipelines, and equipment of Nuclear Power Stations and making them more resistant to erosion-corrosion wear during operation are outlined. Results obtained from comprehensive work on optimizing operational monitoring of the main metal of pipelines used in the condensate-feedwater path of Power units at Nuclear Power Stations equipped with VVER-1000 reactors are presented. The main directions and stages of work on elaborating normative documents and software systems for supporting the personnel of Nuclear Power Stations are determined.
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improvement and optimization of techniques for monitoring erosion corrosion wear of equipment and pipelines at Nuclear Power Stations
Thermal Engineering, 2009Co-Authors: V. N. Lovchev, D. F. Gutsev, G. V. Tomarov, A. A. ShipkovAbstract:We present the concept and main purposes of the Comprehensive Program of Measures on Preventing Failures and Improving the Operational Erosion-Corrosion Resistance of Equipment and Pipelines at Nuclear Power Stations developed at Rosenergoatom, as well as the first results obtained from work on implementing this program. We also describe new approaches, principles, and methods for identifying the dominating mechanism of thinning, for evaluating and extending residual erosion-corrosion service life, and for carrying out calculated-analytical justification of making corrections to typical programs for operational surveillance of the metal of Nuclear Power station pipelines and equipment. Practical possibilities of using the RAMEK software system for simulating local erosion-corrosion processes occurring in the metal of a condensate-feedwater path are demonstrated taking as an example the results of a study on determining factors and dominating mechanism that caused thinning to occur in the metal of the line bypassing the feedwater pipeline of a Nuclear Power station unit.
G. V. Tomarov - One of the best experts on this subject based on the ideXlab platform.
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Results from additional field examination of pipelines carried out at Russian Nuclear Power Stations in accordance with the Mihama program
Thermal Engineering, 2011Co-Authors: V. N. Lovchev, D. F. Gutsev, G. V. Tomarov, A. A. Shipkov, N. S. KoreshkovaAbstract:The results of additional field examination of pipelines obtained in the course of carrying out corrective measures at Russian Nuclear Power Stations in connection with the event that occurred at the Mihama Nuclear Power station are analyzed. The role of these data and the possibility of using them in current and future works carried out by the OAO Rosenergoatom Concern on the problem relating to erosion-corrosion of the metal used in Power units at Nuclear Power Stations are shown.
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principles of development and specific features relating to practical application of software for solving problems connected with erosion corrosion of metal in Power engineering
Thermal Engineering, 2011Co-Authors: G. V. Tomarov, A. A. ShipkovAbstract:Principles used in the development of modern computation codes for calculating erosion-corrosion of Power equipment are considered. Specific features of their practical applications aimed at preventing, revealing, and eliminating erosion-corrosion thinning of the metal of elements used in the units of Power Stations are analyzed. Results obtained from using the domestically developed computation code RAMEK for operating Power units are presented and prospects for implementing it in designing new Power units of Nuclear Power Stations are determined.
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Calculated and experimental substantiation of operating conditions under which adequate erosion resistance of valves used in Power units at Nuclear Power Stations is ensured
Thermal Engineering, 2010Co-Authors: G. V. Tomarov, A. A. Shipkov, N. S. KoreshkovaAbstract:A procedure for revealing factors causing damage to metal and the dominating mechanism through which this damage occurs that was developed earlier is applied for substantiating the operating conditions of valves with D _nom = 800 mm installed in the multiple forced circulation loop of Power units at Nuclear Power Stations equipped with RBMK-1000 reactors under which their resistance to erosion is ensured. Operating conditions under which cavitation erosion may occur are established, and practical proposals on how to prevent damage to the metal of a throttle-control valve’s body are presented.
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operative management of activities on monitoring the erosion corrosion state of elements used in the condensate feedwater path of a Nuclear Power station
Thermal Engineering, 2010Co-Authors: G. V. Tomarov, A V Shutikov, A. A. Shipkov, A I Usanov, Yu M Kanyshev, A V Zelenin, V A Gilev, S V Yakushev, B L Podvolotskii, N. S. KoreshkovaAbstract:New principles, methods, and measures used for preventing the occurrence of failures in elements, pipelines, and equipment of Nuclear Power Stations and making them more resistant to erosion-corrosion wear during operation are outlined. Results obtained from comprehensive work on optimizing operational monitoring of the main metal of pipelines used in the condensate-feedwater path of Power units at Nuclear Power Stations equipped with VVER-1000 reactors are presented. The main directions and stages of work on elaborating normative documents and software systems for supporting the personnel of Nuclear Power Stations are determined.
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improvement and optimization of techniques for monitoring erosion corrosion wear of equipment and pipelines at Nuclear Power Stations
Thermal Engineering, 2009Co-Authors: V. N. Lovchev, D. F. Gutsev, G. V. Tomarov, A. A. ShipkovAbstract:We present the concept and main purposes of the Comprehensive Program of Measures on Preventing Failures and Improving the Operational Erosion-Corrosion Resistance of Equipment and Pipelines at Nuclear Power Stations developed at Rosenergoatom, as well as the first results obtained from work on implementing this program. We also describe new approaches, principles, and methods for identifying the dominating mechanism of thinning, for evaluating and extending residual erosion-corrosion service life, and for carrying out calculated-analytical justification of making corrections to typical programs for operational surveillance of the metal of Nuclear Power station pipelines and equipment. Practical possibilities of using the RAMEK software system for simulating local erosion-corrosion processes occurring in the metal of a condensate-feedwater path are demonstrated taking as an example the results of a study on determining factors and dominating mechanism that caused thinning to occur in the metal of the line bypassing the feedwater pipeline of a Nuclear Power station unit.
V G Kritskii - One of the best experts on this subject based on the ideXlab platform.
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the capacities of a corrosion fatigue monitoring system in managing the service life of steam generators operating at Nuclear Power Stations equipped with a vver 1000m reactor
Thermal Engineering, 2007Co-Authors: G F Banyuk, S I Brykov, O P Arkhipov, V G Kritskii, Yu V Kharitonov, I G Berezina, M V SofinAbstract:We consider the possibilities of using a corrosion-fatigue monitoring system for operatively monitoring the corrosion of heat-transfer tubes in steam generators operating at Nuclear Power Stations equipped with VVER reactors. It is proposed that this system be tested on a Power unit built around a VVER-1000 reactor.
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effect of the quality of the coolant on the operating reliability of items of equipment at Nuclear Power Stations with rbmk 1000 reactors
Thermal Engineering, 2000Co-Authors: V G Kritskii, P S Styazhkin, V M Tishkov, Yu V Garusov, I G Berezina, Yu A Rodionov, S M Kovalev, I K Gasanov, V P Martynov, S P IvanovAbstract:Experience in qualitatively appraising the effect that the quality of the coolant has on the reliability of items of the equipment at Nuclear Power Stations with RBMK-1000 reactors is presented. A correlation between the quality indices of the coolant and the reliability of the most important items of equipment in the multiple forced circulation circuit (MFCC), including the fuel-rod assemblies, is established. The quality of the coolant depends on the operating reliability of the condenser installation, the sensitivity and adequacy of the pickups of automated chemical control (ACC), and the efficiency of condensate polishing. Using correction technologies improves the operating reliability of the items of the equipment.
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using experience in the decontamination of Power units at Nuclear Power Stations with rbmk reactors when decommissioning them
Thermal Engineering, 1999Co-Authors: V M Simanovskii, V G Kritskii, N I Ampelogova, B K Bylkin, Yu A Zverkov, Yu V Garusov, E P Kozlov, V M TishkovAbstract:From an analysis of the experience accumulated in radioactive decontamination of the circuits of multiple forced circulation, it is concluded that this experience and appropriate technologies can be used in decommissioning Power unit no. 1 at the Leningrad Nuclear Power station and other Power units at Nuclear Power Stations with RBMK reactors.
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corrosion of copper alloy tubes in cooling systems of Nuclear Power Stations
Thermal Engineering, 1997Co-Authors: V G Kritskii, P S StyazhkinAbstract:Factors responsible for leakage in steam-turbine condensers of Nuclear Power Stations are analyzed. Causes of corrosive and erosive wear of copper-alloy tubes are discussed. A model is proposed for calculating the corrosion of copper and copper-nickel alloys.
