Relevant bibliographies by topics / Steam generators

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Steam generators'

Author: Grafiati
Published: 4 June 2021
Last updated: 25 July 2025

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Journal articles on the topic "Steam generators"

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Yefimov, Olexander, Larysa Tiutiunyk, Tetyana Harkusha, Tetyana Yesipenko, and Anastasiia Motovilnik. "Mathematical model of the horizontal steam generator PGV-1000." NTU "KhPI" Bulletin: Power and heat engineering processes and equipment, no. 1-2 (December 28, 2022): 53–57. http://dx.doi.org/10.20998/2078-774x.2022.01.06.

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The materials of the article consider the design characteristics of horizontal steam generators PGV-1000 for WWER NPPs. The NPP steam generator, in particular the PGV-1000 steam generator, is a specific heat exchange unit. This unit, together with a nuclear reactor and a steam turbine, is one of the main equipment of multi-circuit (double-circuit) steam turbine NPPs. The steam generator produces working steam using heat dissipated from the reactor core by the cooling medium and sent to the heat exchange surface of the steam generator. NPP steam generators, connecting the contours of the coolan
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Yefimov, Olexander, Larysa Tiutiunyk, Harkusha Tetyana, Yesypenko Tetyana, and Anastasiia Motovilnik. "DESIGN CHARACTERISTICS OF THE HORIZONTAL STEAM GENERATOR PGV-1000." Bulletin of the National Technical University "KhPI". Series: Innovation researches in students’ scientific work, no. 2 (February 27, 2023): 8–12. http://dx.doi.org/10.20998/2220-4784.2022.02.02.

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The materials of the article consider the design characteristics of horizontal steam generators PGV-1000 for WWER NPPs. The NPP steam generator, in particular the PGV-1000 steam generator, is a specific heat exchange unit. This unit, together with a nuclear reactor and a steam turbine, is one of the main equipment of multi-circuit (double-circuit) steam turbine NPPs. The steam generator produces working steam using heat dissipated from the reactor core by the cooling medium and sent to the heat exchange surface of the steam generator. NPP steam generators, connecting the contours of the coolan
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Yefimov, Olexandr, Mykola Pylypenko, Valerii Kavertsev, Tatyana Harkusha, Igor Sydorkin, and Oleksandr Chyzhyk. "COMPARATIVE ANALYSIS OF TECHNICAL, ECONOMIC, WEIGHT, AND SIZE CHARACTERISTICS OF HORIZONTAL AND VERTICAL STEAM GENERATORS FOR 1000 MW NUCLEAR POWER PLANT UNITS." Bulletin of the National Technical University "KhPI". Series: Innovation researches in students’ scientific work, no. 1 (1367) (November 22, 2024): 3–10. http://dx.doi.org/10.20998/2220-4784.2024.01.01.

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A comparative analysis of the technical characteristics and parameters of horizontal and vertical steam generators for reactorinstallations with water coolant in modern 1000 MW NPP power units has been conducted. It is noted that the peculiarities of thedesign schemes and constructions of steam generators in NPP power units with water coolants are significantly influenced by thestrong dependence between the coolant temperature at the steam generator inlet and the pressure in the reactor circuit. Thedependencies of coolant and working substance temperature changes and the amount of heat transfe
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Subhan, Muhammad, Tresna Priyana Soemardi, Topan Setiadipura, Farisy Yogatama Sulistyo, and Hana Subiyah. "The Study of Multiaxial Loading and Damage to the Structure and Materials in the PWR Steam Generator of Nuclear Reactor." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 25, no. 3 (2023): 125. http://dx.doi.org/10.55981/tdm.2023.6963.

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In Pressurized Water Reactor (PWR) Nuclear Power Plants (NPPs), the steam generator is crucial for transferring heat from the primary to secondary cooling systems, vital for steam production to drive turbines, and central to nuclear power safety. This study explores recent research on multi-axial loading, structural integrity, and material durability in PWR steam generators, shedding light on key factors affecting these systems. Common corrosion-related degradation in steam generators often arises from design, material, and water chemistry factors. However, the shift to All Volatile Treatment
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Nordin, A., and M. A. Abd Majid. "Parametric study on the effects of pinch and approach points on heat recovery steam generator performance at a district cooling system." Journal of Mechanical Engineering and Sciences 10, no. 2 (2016): 2134–44. https://doi.org/10.15282/jmes.10.2.2016.17.0201.

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Heat recovery steam generators are important equipment at district cooling plants. The capability of heat recovery steam generators in generating steam influences the steam absorption chiller’s performance. The steam generation capability of the heat recovery steam generators in turn is linked to the values of pinch point and approach point. Hence, a study on the pinch point and approach point for the heat recovery steam generators would be useful in understanding the effects of varying pinch point and approach point values to the heat recovery steam generators’ performance. In relation to thi
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Egorov, Mikle, Ivan Kasatkin, Ivan Kovalenko, Irina Krectunova, Nataliya Lavrovskaya, and Nadezhda Litvinova. "Russian and foreign steam generators for NPP power units with wet steam turbines." E3S Web of Conferences 178 (2020): 01007. http://dx.doi.org/10.1051/e3sconf/202017801007.

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The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam generator design. Design solutions and experience of operation of steam generators of horizontal type accepted in Russia and of vertical type applied by Westinghouse, Combustion Engineering, Siemens, Mitsubishi, Doosan were analyzed within the framework of the present study. It was established that steam generator equipment of horizontal type is characterized by disadvantages of design, technological and operational nature. Thus, horizontal steam generators with dimensions perm
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Egorov, Mikhail Yu. "Vertical steam generators for VVER NPPs." Nuclear Energy and Technology 5, no. 1 (2019): 31–38. http://dx.doi.org/10.3897/nucet.5.33980.

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Steam generators for NPPs are the important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam generator design. This analysis is aimed at the development of recommendations for designing advanced steam generators for future Russian units of NPPs with VVER reactors of increased power. Design solutions and fifty-year experience of operation of 400 steam g
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Egorov, Mikhail Yu. "Vertical steam generators for VVER NPPs." Nuclear Energy and Technology 5, no. (1) (2019): 31–38. https://doi.org/10.3897/nucet.5.33980.

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Steam generators for NPPs are the important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam generator design. This analysis is aimed at the development of recommendations for designing advanced steam generators for future Russian units of NPPs with VVER reactors of increased power. Design solutions and fifty-year experience of operation of 400 steam g
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CHO, SUNG-KEUN, CHANG-SUNG SEOK, BONG-KOOK BAE, and JAE-MEAN KOO. "EVALUATION OF THE HOOP TENSILE PROPERTIES OF A STEAM GENERATOR TUBE." International Journal of Modern Physics B 20, no. 25n27 (2006): 4129–34. http://dx.doi.org/10.1142/s0217979206040970.

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The steam generators in a pressurized water reactor (PWR) are large heat exchangers that use the heat from the primary reactor coolant to make steam on the secondary-side to drive turbine generators. Hoop stress is known to be the main cause of fracture of inner pressurized tubes such as the steam generator tube. However, because the steam generator tube is too small to be manufactured to a standard tensile specimen in the hoop direction, the axial tensile properties of the steam generator tube (or original material properties) instead of hoop tensile properties have been used to estimate the
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Mrzljak, Vedran, Jasna Prpić-Oršić, and Tomislav Senčić. "Change in Steam Generators Main and Auxiliary Energy Flow Streams During the Load Increase of LNG Carrier Steam Propulsion System." Pomorstvo 32, no. 1 (2018): 121–31. http://dx.doi.org/10.31217/p.32.1.15.

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In this paper is presented an analysis of main and auxiliary steam energy flow streams from steam generators during the increase in steam system load at conventional LNG carrier. During the steam system load increase was presented differences in steam pressure and temperature between main and auxiliary steam flow streams. Energy power of the auxiliary flow stream is higher than energy power of the main flow stream only at the lowest steam system loads after which main flow stream takes over primacy at middle and high steam system loads. Cumulative auxiliary energy flow stream was divided on en
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Dissertations / Theses on the topic "Steam generators"

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CABRAL, EDUARDO L. L. "Modelo matematico para o estudo do comportamento dinamico de geradores de vapor de tubos em U com circulacao natural." reponame:Repositório Institucional do IPEN, 1985. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9256.

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Waite, Jason S. "The application of brush seals to steam turbine generators." Thesis, Northumbria University, 1999. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.367419.

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Rummens, Helena E. C. "The thermalhydraulics of tube-support fouling in nuclear steam generators." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1999. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape8/PQDD_0021/NQ48334.pdf.

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Tulloch, Sam. "The use of dispersants in pressurised water reactor steam generators." Thesis, University of Birmingham, 2011. http://etheses.bham.ac.uk//id/eprint/706/.

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Environmental degradation promoted by the presence of sludge piles in the steam generators of Pressurised Water Reactors (PWR) can pose a threat to their safe and continuous operation. The use of dispersants can reduce the rate at which sludge accumulates. Polyacrylic acid (PAA) is currently the only dispersant used in PWRs. Settling rate tests identified several dispersants with the potential to outperform PAA, notably Hydroxyethylidene-1,1-diphosphonic Acid (HEDP). To estimate the dispersant concentration required during plant operation, optimum concentrations were identified for both PAA an
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Rummens, Helena E. C. (Helena Elisabeth Cornelia) Carleton University Dissertation Engineering Mechanical and Aerospace. "The Thermalhydraulics of tube-support fouling in nuclear steam generators." Ottawa, 1999.

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Rehfeldt, Sebastian [Verfasser], and Günter [Akademischer Betreuer] Scheffnecht. "Radiative heat transfer in oxy-fuel steam generators / Sebastian Rehfeldt ; Betreuer: Günter Scheffnecht." Stuttgart : Universitätsbibliothek der Universität Stuttgart, 2016. http://d-nb.info/1118507487/34.

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Damon, Randolph. "A probabilistic fracture mechanics model for the tubing degradation of the Koeberg steam generators." Master's thesis, University of Cape Town, 2004. http://hdl.handle.net/11427/5571.

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Includes bibliographical references (leaves 115-124).<br>The susceptibility of Steam Generator (SG) Tubes (particularly tubes manufactured from Inconel 600) to primary water stress corrosion cracking (PWSCC) has been a major concern to the nuclear industry since 1971, when this phenomenon was first observed outside the laboratory. Since the susceptibility of Inconel 600 to PWSCC in pure water was first established as a certainty, various electricity utilities have devoted considerable resources to determining the exact nature of this degradation phenomenon and to predicting its consequences. W
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RODRIGUES, LUIZ A. H. "Modelagem teorica-experimental da equacao da quantidade de movimento para geradores de vapor de reatores PWR." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10391.

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D'Angelo, Ricardo Andres. "The effects of dispersants on the fouling and the blockage deposits in pressurized water reactor steam generators." Thesis, Paris 6, 2015. http://www.theses.fr/2015PA066767.

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L’acide polyacrylique (APA) est injecté dans les générateurs vapeurs (GV) des réacteurs à eau sous pression pour limiter leur encrassement et leur colmatage. Le but de cette étude est de déterminer l’action de l’APA sur les dépôts présents dans les GV, et le caractère préventif du dispersant vis-à-vis de la formation de dépôts. Dans un premier temps, des dépôts de magnétite ont été soumis aux conditions rencontrées en phase liquide dans les GV, avec et sans APA en boucle d’essai. La concentration en fer en sortie de la boucle augmente significativement à partir d’une injection de 1 mg.kg-1 d’A
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Gerken, Lisa M. "Long-Term Cooling of an SBLOCA: Boron Precipitation in the Core, Boron Dilution in the Steam Generators." Thesis, Virginia Tech, 2014. http://hdl.handle.net/10919/24906.

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When soluble boron is used to control reactivity, there are two particular events which can challenge long-term core cooling (LTCC) during the small break loss-of-coolant accident (SBLOCA): boron precipitation and boron dilution. The initial consequences of the SBLOCA are mitigated by the emergency safety systems, but the core continues to boil. As boron is less volatile than steam, the steam is virtually boron free. All the boron remains in the core, the boron concentration in the core rises. If the solubility limit is reached, precipitation could occur. The boron precipitation event was
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Books on the topic "Steam generators"

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Tapping, R. L. Steam generators: Problems and prognosis. Heat Exchanger Technology Branch, Chalk River Laboratories, 1997.

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Annaratone, Donatello. Steam generators: Description and design. Springer, 2008.

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International Seminar on Horizontal Steam Generators (3rd 1994 Lappeenranta, Finland). Third International Seminar on Horizontal Steam Generators. Lappeenranta University of Technology, 1995.

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International Seminar on Horizontal Steam Generators (4th 1997 Lappeenranta, Finland). Fourth International Seminar on Horizontal Steam Generators. Lappeenranta University of Technology, 1997.

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American Society of Mechanical Engineers. Winter Meeting. Thermal hydraulics of nuclear steam generators/heat exchangers. American Society of Mechanical Engineers, 1988.

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IEEE Power Engineering Society. Power Generation Committee., ed. IEEE recommended practice for functional and performance characteristics of control systems for steam turbine-generator units. Institute of Electrical and Electronics Engineers, 1992.

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International, Seminar on Horizontal Steam Generators (5th 2001 Lappeenranta Finland). Proceedings of Fifth International Seminar on Horizontal Steam Generators. Lappeenranta University of Technology, 2001.

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Junge, Hans Dieter. Pocket dictionary of steam generators.: Taschenwörterbuch Dampferzeuger. Deutsch, Englisch. Verlag für Architektur und technische Wissenschaften, 1986.

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IEEE Power Engineering Society. Power Generation Committee., ed. IEEE recommended practice for functional and performance characteristics of control systems for steam turbine-generator units. Institute of Electrical and Electronics Engineers, 1985.

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Pettigrew, M. J. Flow-induced vibration specifications for steam generators and liquid heat exchangers. Chalk River Laboratories, 1995.

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Book chapters on the topic "Steam generators"

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Jackson, Benjamin W. "Steam Generators." In Power Plant Engineering. Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0427-2_7.

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Kolev, Nikolay Ivanov. "Steam Generators." In Multiphase Flow Dynamics 5. Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-15156-4_8.

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Kolev, Nikolay I. "Steam generators." In Multiphase Flow Dynamics 4. Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-540-92918-5_8.

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Kolev, Nikolay Ivanov. "Steam generators." In Multiphase Flow Dynamics 5. Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-20601-6_8.

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Armbruster, Stanley A. "Steam Turbine Generators." In Power Plant Engineering. Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0427-2_8.

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Guidez, Joël, and Gérard Prêle. "The Steam Generators." In Superphenix. Atlantis Press, 2017. http://dx.doi.org/10.2991/978-94-6239-246-5_12.

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Girard, Sylvain. "Clogging of Recirculating Nuclear Steam Generators." In Physical and Statistical Models for Steam Generator Clogging Diagnosis. Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-09321-5_2.

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Smith, J. E. ’Ed’. "Furnaces and Steam Generators for Industrial Dryers." In Industrial Drying Systems. Springer International Publishing, 2023. http://dx.doi.org/10.1007/978-3-031-31863-4_19.

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Collier, J. G. "Nuclear Steam Generators and Waste Heat Boilers." In Two-Phase Flow Heat Exchangers. Springer Netherlands, 1988. http://dx.doi.org/10.1007/978-94-009-2790-2_22.

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Todreas, Neil E., Mujid S. Kazimi, and Mahmoud Massoud. "Thermal Analysis of Steam Generators and Condensers." In Nuclear Systems Volume II, 2nd ed. CRC Press, 2021. http://dx.doi.org/10.1201/9780429157608-11.

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Conference papers on the topic "Steam generators"

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Evans, S., S. Watson, JF Remark, and F. Ammann. "Steam Generator Chemical Cleaning Experiences (1998 – 2002)." In CORROSION 2003. NACE International, 2003. https://doi.org/10.5006/c2003-03579.

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Abstract Since 1998, a number of steam generator chemical cleanings have been performed in North America and worldwide with the objective reducing the corrosive impact of steam generator secondary side deposits on the steam generator tubes and to improve the heat transfer performance of the steam generator. During the last four years, cleanings have been performed on a number of different types of steam generators. These cleanings used a variety of cleaning processes including high temperature plant heat processes, external heat crevice cleaning processes and bulk deposit removal processes. Ea
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Reinhardt, M., and G. Lewis. "Full Bundle Mechanical Cleaning of Pressurized Water Reactor Steam Generators." In CORROSION 1998. NACE International, 1998. https://doi.org/10.5006/c1998-98331.

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Abstract An improved system for cleaning the upper bundle region of pressurized water reactor steam generators is now available. This system employs high pressure water jets to remove sludge and scale from tube and support plate surfaces and from the broach holes throughout the upper bundle region of steam generators. Benefits of sludge removal can include mitigation of the corrosion process, improvement of plant performance and increased operational stability. The cleaning equipment is installed through existing handholes in the tubesheet region and accesses the upper bundle through flow slot
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Gay, John M. "The Role of Visual Inspection in Planning for Chemical and Mechanical Cleaning." In CORROSION 1998. NACE International, 1998. https://doi.org/10.5006/c1998-98329.

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Abstract From the beginning, the commercial nuclear power industry has faced many difficult challenges. For the Pressurized Water Reactor (PWR) family, steam generator maintenance and repair costs are paramount. Worldwide, utilities have spent billions of dollars on steam generator inspection and repair due to tube corrosion. Several utilities have replaced steam generators. Recent history has shown that most of the corrosion and fouling takes place on the secondary side of steam generators. Visual inspection tools are now providing much of the information necessary to plan when and what metho
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McSweeney, P. "Removal of Copper from Nuclear Steam Generators Using Hydrogen Peroxide." In CORROSION 1993. NACE International, 1993. https://doi.org/10.5006/c1993-93387.

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Abstract Hydrogen peroxide has been recommended for use as an oxidising agent for copper during the chemical cleaning of nuclear steam generators with EDTA-based solutions. However, uncertainty has remained with respect to the effects of process parameters on the stability of the hydrogen peroxide, and with respect to corrosion of Monel 400 tubing during cleaning. A program was established with the objectives to increase understanding on the decomposition of hydrogen peroxide in copper removal solvent and study the corrosion of Monel 400 and other steam generator alloys in the solvent. The eff
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Eber, K. "The Use of Computers for Chemistry and Corrosion Monitoring in the Nuclear Power Industry." In CORROSION 1986. NACE International, 1986. https://doi.org/10.5006/c1986-86071.

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Abstract Corrosion of steam generators in the nuclear power industry has caused increasingly expensive maintenance work during refueling outages. To assist in the control and monitoring of this problem, Northeast Utilities has developed computer programs for tracking steam generator water chemistry and steam generator eddy current inspection data. These programs have allowed detailed analytical studies to be performed which would have been extremely difficult without the use of computers. The paper discusses the capabilities and uses of a chemistry data management system for trending chemistry
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Evans, Sarah E., and S. Dennis Jones. "Deposit Minimization Treatment in Secondary Side Steam Generators for Nuclear Plants." In CORROSION 2015. NACE International, 2015. https://doi.org/10.5006/c2015-05970.

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Abstract Recent advances in chemical cleaning solutions for nuclear power plants have reduced the volume of hazardous waste generated and minimized the impact of cleaning on site schedule and operations. Chemical cleanings are most often utilized in secondary side steam generators to reduce the mass of accumulated deposits, consisting primarily of iron oxides with trace amounts of other metal oxides, for improved thermal performance or mitigation of active corrosion mechanisms as a result of increased deposit loadings. Deposit removal solvents typically consist of a chelating agent combined wi
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MacDonald, S. "Preoperational Chemical Cleaning of Heat Recovery Steam Generators." In CORROSION 2003. NACE International, 2003. https://doi.org/10.5006/c2003-03582.

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Abstract Combined-cycle power generation has become very popular for utilities wishing to increase their power production capacity. Compared to conventional coal-fired units, combined-cycle plants are less expensive, easier to install, have a higher efficiency, and, at the time of this study, are less subject to environmental regulations. An integral component of a combined-cycle unit is the heat recovery steam generator (HRSG). Although heat fluxes in an HRSG are typically lower than in a standard boiler,1 water chemistry issues are just as critical. One topic of extensive discussion among po
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Rocchini, Gabriele. "Some Aspects of the Acid Cleaning of Steam Generators." In CORROSION 1987. NACE International, 1987. https://doi.org/10.5006/c1987-87396.

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Abstract Some problems connected with the acid cleaning of steam generators are discussed. They concern the kinetics of magnetic dissolution, electrochemical controls and the use of a pilot plant for developing this technology. In the first part dealing with magnetite dissolution the chemical and electrochemical mechanisms are examined on the basis of experimental results and it is demonstrated that, though in principle they coexist as parallel reactions, the electrochemical path is kinetically favoured. The phenomenon of reductive magnetite dissolution is very valid in determining the quantit
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Plumley, Arthur L., Wilfred R. Roczniak, and Joseph A. Bacchi. "Update on Materials Performance in RDF-Fired Steam Generators." In CORROSION 1993. NACE International, 1993. https://doi.org/10.5006/c1993-93220.

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Abstract This paper is a progress report covering furnace performance and deposit-tube interaction on waterwall and superheater tube surfaces in Refuse Derived Fuel-fired boilers. The historical development and progress of various methods of wastage protection are described. Both bench scale evaluation and the effects of furnace operation to control deposit build up, are renewed as well as tubing protection methods to provide practical prevention of wastage.
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Robinson, James, and Ge Betz. "Chemical Treatment of Gas Turbine Heat Recovery Steam Generators." In CORROSION 2003. NACE International, 2003. https://doi.org/10.5006/c2003-03492.

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Abstract Selection of an effective chemical treatment program for heat recovery steam generators requires an analysis of the equipment provided, the operating requirements of the system, and the personnel and equipment available to control the water chemistry. This paper discusses the advantages and limitations of the various treatment approaches commonly employed, and provides a flow diagram to assist in selecting a suitable program for various HRSG system operating requirements.
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Reports on the topic "Steam generators"

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Geffraye, G., P. Bazin, and P. Pichon. CCFL in hot legs and steam generators and its prediction with the CATHARE code. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/107026.

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Uvan Catton, Vijay K. Dhir, Deepanjan Mitra, Omar Alquaddoomi, and Pierangelo Adinolfi. Development of Design Criteria for Fluid Induced Structural Vibrations in Steam Generators and Heat Exchangers. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/827838.

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Catton, Ivan, Vijay K. Dhir, O. S. Alquaddoomi, Deepanjan Mitra, and Pierangelo Adinolfi. Development of Design Criteria for Fluid Induced Structural Vibration in Steam Generators and Heat Exchangers. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/822365.

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Belle R. Upadhyaya and J. Wesley Hines. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/832717.

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Belle R. Upadhyaya and J. Wesley Hines. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/832721.

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Kreider, M. A., G. A. White, R. D. Varrin, and P. J. Ouzts. Heat transfer characteristics of porous sludge deposits and their impact on the performance of commercial steam generators. Office of Scientific and Technical Information (OSTI), 1998. http://dx.doi.org/10.2172/329562.

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Geelhood, B. D., and K. H. Abel. Neutron measurements of the fuel remaining in the TMI II once-through steam generators (OTSG'S). Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/6456962.

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Upadhyaya, Belle R., J. Wesley Hines, and Baofu Lu. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/843182.

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Kurtz, R., R. Clark, E. Bradley, et al. Steam Generator Tube Integrity Program/Steam Generator Group Project. Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6853141.

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Adams, J. P., and E. S. Peterson. Steam generator secondary pH during a steam generator tube rupture. Office of Scientific and Technical Information (OSTI), 1991. http://dx.doi.org/10.2172/10139132.

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