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Journal articles on the topic 'Steam generators'

Author: Grafiati

Published: 4 June 2021

Last updated: 25 July 2025

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1

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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2

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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3

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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4

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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5

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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6

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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7

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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8

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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9

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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10

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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11

Skalozubov, V. I., O. M. Vierinov, I. M. Verbylo, V. Yu Kochnieva, and A. V. Kanivets. "Qualification of Management Strategies for Continuous Blackout Accident at Nuclear Power Plants with VVER." Nuclear Power and the Environment 29 (2024): 23–28. http://dx.doi.org/10.31717/2311-8253.24.1.3.

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The most important lesson of the Fukushima accident for the safety of nuclear power is the need to improve/modernize management strategies for continuous blackout accidents at nuclear facilities. The deterministic analysis of the continuous blackout accident at nuclear power plants with VVER-1000/320, carried out by the operating organization of the Ukrainian NPPs, recognized that the emergency supply system of steam generators is critical for safety. The work analyzes and qualifies (substantiates) the known modernizations of management strategies for the continuous blackout accidents at VVER

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12

Kovalchuk, V., I. Kozlov, O. Dorozh, and A. Machkov. "EFFICIENCY OF STEAM GENERATORS AT NUCLEAR POWER PLANTS." Odes’kyi Politechnichnyi Universytet Pratsi 2, no. 64 (2021): 28–35. http://dx.doi.org/10.15276/opu.2.64.2021.04.

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The possibility of a comprehensive assessment of steam generators efficiency at nuclear power plants with water-water reactors, based on the indicator of OEE (overall equipment effectiveness) is considered. It is proposed to consider efficiency as the probability of functioning from the standpoint of availability, performance and product quality.The aim of the work is to evaluate the possibility of using the OEE indicator to analyze the efficiency of NPP steam generators in complex conditions: reactor − steam generator − turbine. Achieving this goal will provide a comprehensive indicator of mo

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13

Green, S. J., and G. Hetsroni. "PWR steam generators." International Journal of Multiphase Flow 21 (December 1995): 1–97. http://dx.doi.org/10.1016/0301-9322(95)00016-q.

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14

Blokhina, A., S. Lyakishev, and O. Korotkova. "POWER CALCULATION OF STRAIGHT-PIPE STEAM GENERATOR WITH SODIUM COOLANT." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2021, no. 1 (2021): 152–61. http://dx.doi.org/10.55176/2414-1038-2021-1-152-161.

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The article investigates the influence of coolant flow profile nonlinearity through straight-pipe steam generators tube assembly for fast neutron reactor with sodium coolant on heat exchanger power. When designing steam generators, a very important task is to correctly calculate the output parameters of the steam generator, especially the power. For the plants without reference solutions it is necessary to perform a deep analysis of the factors affecting on calculated parameters and to incorporate these parameters in the codes. An example of a new plant that do not have analogues is a shell-ty

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15

Korolev, Vladimir I. "ANALYSIS OF THERMOHYDRAULIC CHARACTERISTICS OF STEAM GENERATOR CASSETTES OF THE RITM-200 REACTOR PLANTS OF THE UNIVERSAL NUCLEAR ICEBREAKERS." Vestnik Gosudarstvennogo universiteta morskogo i rechnogo flota imeni admirala S. O. Makarova 14, no. 5 (2022): 759–74. http://dx.doi.org/10.21821/2309-5180-2022-14-5-759-774.

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Currently, a new icebreaking fleet including universal nuclear icebreakers of the new generation of project 22220 is being intensively built in Russia. The nuclear icebreakers of this project such as “Arctic” and “Siberia” are already in operation. The “Ural” “nuclear icebreaker is almost ready for commissioning. “Yakutia” and “Chukotka” icebreakers as well as the icebreaker-leader of project 10510 are under construction. The integrated layout of the main equipment of the reactor plant had been used for the first time on the nuclear icebreakers of the new generation of these projects. The appl

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16

Lee, Ouk Sub, Hyun Su Kim, Jong Sung Kim, Tae Eun Jin, Hong Deok Kim, and Han Sub Chung. "Plastic Limit Load Solutions for Surface Crack in the Steam Generator Tubes." Key Engineering Materials 297-300 (November 2005): 1704–12. http://dx.doi.org/10.4028/www.scientific.net/kem.297-300.1704.

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Operating experience of steam generators has shown that cracks of various morphologies frequently occur in the steam generator tubes. These cracked tubes can stay in service if it is proved that the tubes have sufficient safety margin to preclude the risk of burst and leak. Therefore, integrity assessment using exact limit load solutions is very important for safe operation of the steam generators. This paper provides global and local limit load solutions for surface cracks in the steam generator tubes. Such solutions are developed based on three-dimensional (3-D) finite element analyses assum

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17

LEE, CHOON YEOL, JOON WOO BAE, YOUNG SUCK CHAI, and KYOOSIK SHIN. "EXPERIMENTAL STUDY ON IMPACT FRETTING WEAR OF INCONEL TUBES UNDER HIGH TEMPERATURE AND PRESSURE." International Journal of Modern Physics B 25, no. 31 (2011): 4253–56. http://dx.doi.org/10.1142/s0217979211066702.

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In nuclear power plant, fretting wear caused by flow induced vibration (FIV) accompanied with impact force can make serious problems between U -tubes and egg-crates which are located in steam generators. In order to guarantee the reliability of the steam generator, design based on consideration of the damage due to the fretting wear of the U -tube is inevitable. The purpose of this study is to elucidate fretting wear mechanism qualitatively and quantitatively. First, finite element models are developed to analyze the dynamic characteristics and estimate the impact force in steam generators. Ba

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18

Walter, Heimo, and Wladimir Linzer. "Flow Stability of Heat Recovery Steam Generators." Journal of Engineering for Gas Turbines and Power 128, no. 4 (2004): 840–48. http://dx.doi.org/10.1115/1.2179469.

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This paper presents the results of theoretical flow stability analyses of two different types of natural circulation heat recovery steam generators (HRSG)—a two-drum steam generator—and a HRSG with a horizontal tube bank. The investigation shows the influence of the boiler geometry on the flow stability of the steam generators. For the two-drum boiler, the steady-state instability, namely, a reversed flow, is analyzed. Initial results of the investigation for the HRSG with a horizontal tube bank are also presented. In this case, the dynamic flow instability of density wave oscillations is anal

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19

Dolganov, K. S., A. A. Krutikov, and A. V. Nikolaeva. "Numerical study of convective heat transfer between core and steam generator in severe accident with loss of heat removal to secondary side of VVER reactors." Izvestiâ Akademii nauk SSSR. Ènergetika, no. 4 (December 21, 2024): 88–109. https://doi.org/10.31857/s0002331024040063.

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The article discusses the possibility of overheating and failure of heat exchanging tubes in VVER steam generators in the course of severe accidents. The importance of this phenomenon is due to the risk of bypassing the containment by radioactive substances. Natural convection of superheated steam in the hot leg of the main circulation loop is considered as the major mechanism for heat transfer from the core to steam generators. To model convective flows and steam temperature distribution in a system, three-dimensional CFD codes are used. The simulation results demonstrate that the intensity o

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20

Smykov, V., S. Kanukhina, and K. Legkikh. "THE PHYSICAL MODEL OF MASS TRANSFER CORROSIVE HYDROGEN IN FAST REACTOR STEAM GENERATORS OF THE SODIUM-WATER TYPE." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2021, no. 3 (2021): 206–12. http://dx.doi.org/10.55176/2414-1038-2021-3-206-212.

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For timely and prompt detection of the inter-circuit depressurization of the steam generator of the “sodium-water” type in the 2nd circuit, continuous monitoring of the content of hydrogen, as a product of the interaction of sodium with water, is carried out in all operating modes. However, in reality, the main source of hydrogen in the sodium of the 2nd circuit is the process of electrochemical corrosion of 10X2M steam generator steel in a steam-water medium, the speed of which is never zero and is controlled at the minimum achievable level by means of the water-chemical regime of the 3rd cir

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21

Efimov, Olexander, Valerii Kavertsev, and Petro Lifshyts. "Methods of the Strength Computation for the Covers, Bottoms, Assemblies and Elements of the Structure of Steam Generators Used by the Two-Loop Nuclear Power Plants with BBEP-1000 Reactors." NTU "KhPI" Bulletin: Power and heat engineering processes and equipment, no. 3-4 (December 28, 2022): 29–34. http://dx.doi.org/10.20998/2078-774x.2022.03.05.

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This scientific paper gives a review of the available methods and approaches used for the strength computation of the covers, bottoms, assemblies and elements of the structures of steam generators of the two-loop NPPs with BBEP-1000 reactors. For most assemblies and elements of the structures of steam generators of NPPs, the main strains arising in them are the consequences of the uniform internal and external pressures. However, in many cases the assemblies and elements of the structures of steam generators of NPPs can also be exposed to additional loads (weight loads, efforts and moments tha

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22

Rice, I. G. "Split Stream Boilers for High-Temperature/High-Pressure Topping Steam Turbine Combined Cycles." Journal of Engineering for Gas Turbines and Power 119, no. 2 (1997): 385–94. http://dx.doi.org/10.1115/1.2815586.

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Research and development work on high-temperature and high-pressure (up to 1500°F TIT and 4500 psia) topping steam turbines and associated steam generators for steam power plants as well as combined cycle plants is being carried forward by DOE, EPRI, and independent companies. Aeroderivative gas turbines and heavy-duty gas turbines both will require exhaust gas supplementary firing to achieve high throttle temperatures. This paper presents an analysis and examples of a split stream boiler arrangement for high-temperature and high-pressure topping steam turbine combined cycles. A portion of the

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23

Povarov, P. V. "Justification of level values in steam generators with V-392m reactor unit during normal operation and normal operation disturbance." Global Nuclear Safety 15, no. 1 (2025): 67–73. https://doi.org/10.26583/gns-2025-01-07.

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The ability to carry the load during transients without achieving the operating conditions of the safety and emergency control action of the reactor is called the dynamic stability of the NPP power unit. Water level control in steam generators RU VVER-1200 (V-392M) is carried out to maintain a balance between steam removal, purging and water supply. A change in the water level in the steam generator caused by transients can lead to the achievement of technological protection and blocking settings, followed by the shutdown of the main circulation pump and a reduction in load. An analysis of the

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SANTOS, RICARDO B., and PETER W. HART. "Case study: Paper mill power plant optimization—balancing steam venting with mill demand." June 2020 19, no. 6 (2020): 317–21. http://dx.doi.org/10.32964/tj19.6.317.

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Most Power departments are tasked with generating steam to support mill wide operations, gener-ate electricity, and reduce operating costs. To accomplish these tasks, power boilers generate high pressure steam that is reduced to intermediate and low pressures for process utilization in the mill by means of steam turbine generator extraction or pressure reducing valves. The most economical method to reduce steam pressure is the use of steam turbine generators, as electricity is generated from the steam when it is reduced in pressure. Electricity that is produced by these generators provides a s

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25

Sahin, Huseyin Emre, and Harun Kemal Ozturk. "A Novel Model for U-Tube Steam Generators for Pressurized Water Reactors." Energies 18, no. 6 (2025): 1506. https://doi.org/10.3390/en18061506.

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A novel model was proposed for U-Tube Steam Generators in Pressurized Water Reactors to be utilized in dynamics and control studies. The steam generator was divided into 14 nodes and investigated by applying mass and energy conservation equations in differential form. A system of nonlinear differential equations was obtained. This equation system was numerically simulated using the Julia programming language through a fourth order Runge–Kutta method. Accurate values for thermodynamic properties were taken from the Coolprop library, eliminating the need to take constant values or linear interpo

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Schäfer, Dominik, Larissa Queda, Volker Nischwitz, Qingping Fang, and Ludger Blum. "Origin of Steam Contaminants and Degradation of Solid-Oxide Electrolysis Stacks." Processes 10, no. 3 (2022): 598. http://dx.doi.org/10.3390/pr10030598.

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Two once-through steam generators and a combination of a steam generator and a gas preheater for supplying feed gases to solid-oxide electrolysis stacks were evaluated for their carryover characteristics of contaminants from the feed-water into the steam phase. The concentrations of various trace impurities in the steam were determined by sampling the steam condensates and screening them with inductively coupled plasma–mass spectrometry for 19 elements and liquid ion chromatography and continuous flow analysis for chloride and ammonium. Steam-soluble species such as boric acid undergo complete

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Arzhaev, Alexander, Alexey Arzhaev, Valentin Makhanev, et al. "Possible in-service damages of steam generators at VVER-1000 and VVER-1200 NPP units and their impact on long-term operation." E3S Web of Conferences 209 (2020): 03005. http://dx.doi.org/10.1051/e3sconf/202020903005.

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Specific features of corrosion-mechanical damages of primary circuit header to steam generator vessel branch welds at VVER-1000 NPPs and their impact on safety and economic efficiency during long-term operation are analysed. Measures to avoid the damages for similar zones of VVER-1200 steam generators are discussed.

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28

Langston, Lee S. "Cogeneration: Gas Turbine Multitasking." Mechanical Engineering 134, no. 08 (2012): 50. http://dx.doi.org/10.1115/1.2012-aug-4.

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This article describes the functioning of the gas turbine cogeneration power plant at the University of Connecticut (UConn) in Storrs. This 25-MW power plant serves the 18,000 students’ campus. It has been in operation since 2006 and is expected to save the University $180M in energy costs over its 40-year design life. The heart of the UConn cogeneration plant consists of three 7-MW Solar Taurus gas turbines burning natural gas, with fuel oil as a backup. These drive water-cooled generators to produce up to 20–24 MW of electrical power distributed throughout the campus. Gas turbine exhaust hea

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Al-Dabbas, Mohammad Awwad Ali. "The Availability of Hybrid Nano Adsorption-Multi Stage Ejector Cooling Cycle with a Different Type of Steam Generator." Mathematical Modelling of Engineering Problems 8, no. 5 (2021): 826–36. http://dx.doi.org/10.18280/mmep.080520.

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Ejectors are a kind of pump that does not have any moving components. In certain cases, the motor fluid may be a liquid, steam, or another gas. The research focuses on using nano adsorption combined with a multi ejector to fuel a sophisticated nano adsorption power plant, which is equipped with three shapes of steam boiler generators. The simulation was accomplished by implementing it with the cooperation of the two programs MATLAB A and MATLAB B, together with a solid flow. To raise the temperature of the working fluid before it enters the generator, a jet pump is positioned before the genera

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Poljak, Igor, Josip Orović, Vlatko Knežević, and Jure Vulić. "The Low Duty Centrifugal Compressor Control System and its Impact on the Surge Pressure." Journal of Maritime & Transportation Science 57, no. 1 (2019): 47–55. http://dx.doi.org/10.18048/2019.57.03.

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This paper presents an analysis of the low duty compressor for marine steam generators and its running conditions. The analysed low duty compressor was observed under three different running zones caused by a throttled flow towards main steam generators. All examples were explained according to real exploitation conditions. As the low duty compressor has the highest influence on the flame stability for the main steam generators while running, it is very important to observe the constant flow towards the main steam generators. Possible flow fluctuation implies instabilities which are explained

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Osintsev, Konstantin, Sergey Aliukov, and Sulpan Kuskarbekova. "Investigation of Operation of Coil-Flow Steam Generator of Serpentine Type in Conditions of Low Ambient Temperatures." International Journal of Heat and Technology 39, no. 4 (2021): 1164–72. http://dx.doi.org/10.18280/ijht.390414.

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Stationary and mobile steam generators are widely used in low ambient temperatures, for example in areas described by the Köppen world map as subarctic. Such equipment is often used in oil and gas fields. At the moment, the existing standard boiler plants are outdated. The purpose of this work is an experimental study of a coiled-type direct-flow steam generator developed by the authors in the winter period at low ambient temperatures. The tasks to be solved to achieve the goal are associated with obtaining experimental data at different operating modes of the installation, their processing an

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32

LUCAN, Dumitra. "Application of CANDU steam generator research experience in the field of SMR steam generators." EMERG - Energy. Environment. Efficiency. Resources. Globalization 9, no. 2 (2023): 7–26. http://dx.doi.org/10.37410/emerg.2023.2.01.

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Au-Yang, M. K. "Flow-Induced Wear in Steam Generator Tubes—Prediction Versus Operational Experience." Journal of Pressure Vessel Technology 120, no. 2 (1998): 138–43. http://dx.doi.org/10.1115/1.2842231.

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Many nuclear steam generators have accumulated more than 10 effective-full-power-years of operation. Eddy-current inspections revealed that a number of these steam generator tubes, notably those located in high local cross-flow regions, have indications of wear at some support plate elevations after 5 to 10 yr of effective-full-power operations. In the last 5 yr, a number of technical papers on nonlinear tube bundle dynamics has been published to address the effect of tube and support plate interactions. At the same time, test data relating wear and tube wall thickness losses for different mat

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34

Tieszen, S., H. Merte, V. S. Arpaci, and S. Selamoglu. "Crevice Boiling in Steam Generators." Journal of Heat Transfer 109, no. 3 (1987): 761–67. http://dx.doi.org/10.1115/1.3248155.

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Experimental results are presented on the influence of confinement (normal to heated surface) on nucleate boiling in forced flow. The forced flow conditions and confinement geometry studied are similar to those found for boiling between a primary-fluid tube and a tube-support plate in steam generators of pressurized-water-reactor nuclear power plants. Visual observations of the boiling process within the confined region (crevice) between the tube and its support plate, obtained by high-speed photography, are related to simultaneous two-dimensional temperature maps of the hot primary-fluid-tube

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35

Rodríguez, Martín A. "Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: a review." Corrosion Reviews 38, no. 3 (2020): 195–230. http://dx.doi.org/10.1515/corrrev-2020-0015.

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AbstractNuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators

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36

Rep, Ivan, Tomislav Tomašić, and Darko Barilar. "Sludge Deposit Mapping for Steam Generators." Journal of Energy - Energija 65, no. 1-2 (2022): 75–82. http://dx.doi.org/10.37798/2016651-2129.

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During plant operation, corrosion products from feedwater, drain and condensate system accumulate on the secondary side of steam generator in form of scaled deposits around the tubes and sludge piles on top of the tubesheet. These deposits increase potential for corrosion, affect fluid flow and reduce heat transfer efficiency of the steam generator. Using data obtained during periodical eddy current examination of steam generator tubing, information on sludge deposit location and thickness is extracted from low frequency absolute channels. Sludge deposits can be detected over the whole length

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Krasniqi-Alidema, Drenusha, Risto Filkoski, and Marigona Krasniqi. "Exergy efficiency analysis of lignite-fired steam generator." Thermal Science 22, no. 5 (2018): 2087–101. http://dx.doi.org/10.2298/tsci180131265k.

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The operation of steam generators and thermal power plants is commonly evaluated on a basis of energy analysis. However, the real useful energy loss cannot be completely justified only by the First law of thermodynamics, since it does not differentiate between the quality and amount of energy. The present work aims to give a contribution towards identification of the sources and magnitude of thermodynamic inefficiencies in utility steam generators. The work deals with a parallel analysis of the energy and exergy balances of a coal-fired steam generator that belongs to a 315 MWe power generatio

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Molotov, I. M., A. I. Schastlivtsev, L. V. Yamshchikova, and I. A. Molotova. "Development of an automated system for experimental investigation of thermal processes in a hydrogen-oxygen steam generator." Journal of Physics: Conference Series 2039, no. 1 (2021): 012023. http://dx.doi.org/10.1088/1742-6596/2039/1/012023.

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Abstract The paper presents the results of the development and creation of an automated system of scientific research (ASSR). It provides experimental studies of heat and mass transfer processes in a hydrogen-oxygen steam generator (HOSG). The most relevant fields of application of hydrogen-oxygen steam generators are considered. The paper discusses the most relevant areas of application of hydrogen-oxygen steam generators, scientific and technical barriers to the introduction of technology and the features of the construction of ASSR for experimental research. The schematic diagram of the pri

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Shi, Jin Hua. "Structural Integrity Role in Plant Life Extension - A Case Study." Applied Mechanics and Materials 750 (April 2015): 295–306. http://dx.doi.org/10.4028/www.scientific.net/amm.750.295.

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The steam generators at Advanced Gas-Cooled Reactor (AGR) nuclear power stations in the UK are potentially life-limiting components. Enhancing the capability to monitor the steam generators has been identified as having the potential to provide key evidence in justifying the extension of the generating lifetime of the stations. It has been proposed to install new temperature measuring instrumentation to monitor reactor gas temperature and to provide additional data regarding steam generator operating conditions. The modification will be to introduce thermocouples to the bore of an intact steam

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Kudryavtsev, A. S., S. A. Suvorov, D. A. Artemieva, and R. M. Ramazanov. "Corrosion resistance of 12% chrome steel under the operation conditions of a steam generator of a reactor plant with sodium coolant." Voprosy Materialovedeniya, no. 3(111) (November 1, 2022): 131–47. http://dx.doi.org/10.22349/1994-6716-2020-104-4-131-147.

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The influence of an aqueous medium and superheated steam on the corrosion resistance and resistance to corrosion-mechanical destruction of 07Kh12NMFB steel in various operating modes of a steam generator of a promising high-power sodium-cooled reactor plant has been studied. Steel of this grade meets the requirements for the operation of heat exchange pipes and vessel elements of direct-flow steam generators of a reactor plant in terms of corrosion resistance and corrosion-mechanical strength.

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Leis, D. M., M. J. Boss, and M. P. Melsert. "Medway: A High-Efficiency Combined Cycle Power Plant Design." Journal of Engineering for Gas Turbines and Power 117, no. 4 (1995): 713–23. http://dx.doi.org/10.1115/1.2815457.

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The Medway Project is a 660 MW combined cycle power plant, which employs two of the world’s largest advanced technology MS9001FA combustion turbine generators and an advanced design reheat steam turbine generator in a power plant system designed for high reliability and efficiency. This paper discusses the power plant system optimization and design, including thermodynamic cycle selection, equipment arrangement, and system operation. The design of the MS9001FA combustion turbine generator and the steam turbine generator, including tailoring for the specific application conditions, is discussed

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Roussel, Guy, and Leon Cizelj. "Reliability of Sampling Inspection Schemes Applied to Replacement Steam Generators." Journal of Pressure Vessel Technology 129, no. 1 (2006): 109–17. http://dx.doi.org/10.1115/1.2389027.

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The basis for determining the size of the random sample of tubes to be inspected in replacement steam generators is revisited in this paper. A procedure to estimate the maximum number of defective tubes left in the steam generator after no defective tubes have been detected in the randomly selected inspection sample is proposed. A Bayesian estimation is used to obtain closed-form solutions for uniform, triangular, and binomial prior densities describing the number of failed tubes in steam generators. It is shown that the particular way of selecting the random inspection sample (e.g., one sampl

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Mantelli, Luca, Alberto Traverso, Katia Lupinetti, Franca Giannini, Luigi Monica, and Sara Anastasi. "A virtual reality learning platform for steam generators." E3S Web of Conferences 414 (2023): 02010. http://dx.doi.org/10.1051/e3sconf/202341402010.

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Virtual reality (VR) has proven to be an effective tool for industrial training, offering immersive and interactive learning experiences. However, it is important to accurately simulate the behavior of the equipment in order to provide realistic training activities to the users. On these premises, the PITSTOP project aims at developing an immersive learning tool, based on the integration of dynamic models and a VR environment. Following this methodology, the first learning platform for industrial-scale steam generators was created. Adopting a mixed physics-based data-driven approach, a fast bu

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Hossu, Daniela, Ioana Făgărășan, Andrei Hossu, and Sergiu St Iliescu. "Evolved Fuzzy Control System for a Steam Generator." International Journal of Computers Communications & Control 5, no. 2 (2010): 179. http://dx.doi.org/10.15837/ijccc.2010.2.2473.

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Poor control of steam generator water level is the main cause of unexpected shutdowns in nuclear power plants. Particularly at low powers, it is a difficult task due to shrink and swell phenomena and flow measurement errors. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters vary with operating conditions. Therefore, there is a need to systematically investigate the problem of controlling the water level in the steam generator in order to prevent such costly reactor shutdowns. The objective of this paper is to design, evaluate and impleme

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Dechamps, P. J. "Modelling the Transient Behaviour of Heat Recovery Steam Generators." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 209, no. 4 (1995): 265–73. http://dx.doi.org/10.1243/pime_proc_1995_209_005_01.

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This paper describes a method used to compute the transient performances of assisted circulation heat recovery steam generators. These heat recovery steam generators are composed of several heat exchangers, each of which is a bundle of tubes. The method presented here treats each heat exchanger in a similar way, replacing the bundle of tubes with an ‘equivalent’ linear heat exchanger. This equivalent linear heat exchanger is then discretized in as many slices as required by the accuracy. The mass and enthalpy equations on each of these control volumes are solved by a fully explicit numerical m

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Egorov, Mikhail Yur’evich. "Vertical steam generators for VVER NPPs." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2018, no. 3 (2018): 88–99. http://dx.doi.org/10.26583/npe.2018.3.08.

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Trunov, N. B., S. B. Ryzhov, and S. E. Davidenko. "Horizontal steam generators: Problems and prospects." Thermal Engineering 58, no. 3 (2011): 179–83. http://dx.doi.org/10.1134/s004060151103013x.

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Lorenzini, E., M. Spiga, G. Iadarola, and F. D'Auria. "Density wave instabilities in steam generators." Annals of Nuclear Energy 18, no. 1 (1991): 31–42. http://dx.doi.org/10.1016/0306-4549(91)90035-v.

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Fennell, E., K. Kozminski, M. Bajpai, et al. "Sequential tripping of steam turbine generators." IEEE Transactions on Power Delivery 14, no. 1 (1999): 132–41. http://dx.doi.org/10.1109/61.736702.

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Strusnik, Dusan, Igor Kustrin, and Jurij Avsec. "Off-design flow analysis of cogeneration steam turbine with real process data." Thermal Science 26, no. 5 Part B (2022): 4107–17. http://dx.doi.org/10.2298/tsci2205107s.

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This paper presents the concept of reconstruction of the existing coal-fired combined heat and power plant to comply with new European environmental policies. The existing coal-fired boiler will be replaced by two new dual pressure heat recovery steam generators, which will utilize the exhaust gas heat from two new gas turbines. The steam from the heat recovery steam generators will be fed to the existing steam turbine. After the reconstruction, the nominal turbine inlet steam mass-flow of 40 kg/s will be reduced to 30 kg/s. During periods of low heat demand, only one gas turbine and one heat

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