Journal articles: '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 coolant and the working substance, equally belong to each of them. The heat-absorbing medium in the steam generator is the working substance (water, steam). PGV-1000 type NPP steam generators with pressurized water reactors produce dry saturated steam. The requirement to maintain high purity of the coolant is due to the heat transfer surfaces of such steam generators made of austenitic stainless steel with electropolished surfaces. The design characteristics of modern horizontal steam generators such as PGV-1000 of various modifications provide high technical and economic performance of NPP units with WWER-1000 and high maintainability, which allows to extend the service life of domestic NPPs.

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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 permissible for railroad transportation and, for VVER-1200 with reactor vessel diameter equal to 5 m, by water transport as well, have exhausted the possibilities for further significant increase of the per unit electric power. The demonstrated advantages of vertical-type steam generators are as follows: 1) absence of stagnant zones within the second cooling circuit; 2) uniformity of heat absorption efficiency of the heating surface that ensures improved conditions for moisture separation; 3) increased temperature drop with parameters of generated steam elevated by 0.3 – 0.4 MPa. Conclusion was made on the advisability of introduction of steam generators with vertical-type layout in the Russian nuclear power generation.

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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 coolant and the working substance, equally belong to each of them. The heat-absorbing medium in the steam generator is the working substance (water, steam). PGV-1000 type NPP steam generators with pressurized water reactors produce dry saturated steam. The requirement to maintain high purity of the coolant is due to the heat transfer surfaces of such steam generators made of austenitic stainless steel with electropolished surfaces. WWER reactors do not allow the coolant to boil in the core, so the temperature of the coolant at the outlet of the reactor (at the inlet to the steam generator) is always lower than the saturation temperature corresponding to the water pressure in the coolant circuit. Underheating of the coolant to the saturation temperature (approximately 25 ÷ 30 °С) guarantees the exclusion of vaporization even in the most loaded reactor channels. The design characteristics of modern horizontal steam generators such as PGV-1000 of various modifications provide high technical and economic performance of NPP units with WWER-1000 and high maintainability, which allows to extend the service life of domestic NPPs.

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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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Egorov, Mikhail Yu. "Vertical steam generators for VVER NPPs." Nuclear Energy and Technology 5, no. 1 (March 20, 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 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. Advantages and drawbacks of both types of equipment determining the development of conditions of the operating processes were also identified and systematized. Currently NPPs equipped with VVER are characterized with extended surface area of containment shells due to the application of four-loop design configuration and horizontal-type steam generators. It was established that steam generator equipment of horizontal type is characterized by such inherent disadvantages of design, technological and operational nature as the following: 1) small height and volume of the vapor space above the evaporation surface reducing separation capabilities and the capacity of the equipment as a whole; 2) impossibility of organizing separate single-phase pre-boiling section. Because of the above, horizontal steam generators with dimensions permissible for railroad transportation and, for VVER-1200 with reactor vessel diameter equal to 5 m, by water transport as well, have exhausted the possibilities for further significant increase of the per unit electric power. The demonstrated advantages of vertical-type steam generators were as follows: 1) absence of stagnant zones within the second cooling circuit, and, consequently, of hold-ups in them; 2) uniformity of heat absorption efficiency of the heating surface ensuring, as well, improved conditions for moisture separation; 3) high degree of moisture removal from steam-water mixture due to the combination of moisture separating elements of chevron and swirl-vane types; 4) increased temperature drop with parameters of generated steam elevated by 0.3 – 0.4 MPa. Conclusion was made on the advisability of introduction of steam generators with vertical-type layout in the Russian nuclear power generation. Practical tasks that need to be addressed in order to ensure introduction of vertical steam generators at NPPs with high-power VVER reactors were formulated.

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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 monitoring the efficiency of steam generating systems and have a tool for systematic monitoring of steam generators. To assess the organizational and environmental efficiency of the organizational structure, individual, group and integrated indicators are proposed, which reflect the share or decrease of the absolute indicator in the system compared to the baseline. The study is based on the analysis of long-term performance of units with steam generators PG-1000, which are comparable. It is shown that the main element of the steam generation system, which determines its efficiency, is the heat generating source. The contribution to the efficiency of all aspects of operation is estimated. It is shown that the efficiency index of OEE allows to characterize the efficiency of steam generators operation at nuclear power plants with water-water reactors, and can be used to monitor and control the process of their operation. In result of research, it is defined that steam generator efficiency increases in process of achievement of the maximum value of its productivity.

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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 (October 30, 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 fracture properties of a steam generator tube. In this study, we have conducted not only axial tensile tests but also ring tensile tests. From these test, both the axial and hoop tensile properties of steam generator tubes were obtained, and the reliability of the hoop tensile properties were confirmed by burst test of a real steam generator tube.

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Walter, Heimo, and Wladimir Linzer. "Flow Stability of Heat Recovery Steam Generators." Journal of Engineering for Gas Turbines and Power 128, no. 4 (March 1, 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 analyzed.

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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 (March 26, 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-type steam generator for perspective fast neutron plants with liquid metal sodium coolant. The application of new solutions in steam generators design requires experimental and calculational justification of thermal hydraulic with the use of modern calculation codes. Power calculation of steam generator is carried out by thermohydraulic code “KORSAR/GP”, “PGN-2K”. One of the assumptions in coolant path parameters calculation model (tube space) is a uniform velocity profile by cross-section of tube assembly. It’s also accepted, that each heat exchange tube has the same expense of feed water. On the other hand calculational CFD and experimental studies at aerodynamic model of steam generator showed the presence of significant unevenness of coolant expense by tube space cross-section which is not taken into account in thermohydraulic calculations. The article contains the methodic of accounting for the known uneven coolant flow profile by tube space cross-section in liquid metal steam generator calculation. Based on the results obtained, measures to improve power output and reliability are proposed.

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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 (December 14, 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 application of the new principle of equipment layout required switching to a fundamentally new method of forming the heat exchange surface of steam generators. As a result, straight-tube modular structures assembled into cassettes of steam generators were used. The approach to providing feed water supply and steam removal from steam generators has also changed, which significantly affects the thermohydraulic processes in the cassettes and leads to a decrease in the temperature of steam at the outlet of steam generators. In addition, the heat exchange surface of the modules in the longitudinal section forms annular channels with two-way heating by a coolant, which also affects the steam generators characteristics formation. In particular, the coefficients of heat transfer and heat transfer over the phase sections of heat exchange, the average logarithmic heat heads and the distribution of the heat exchange surfaces of the sections have changed compared to the previously used coil steam generators. At the same time, the hydraulic resistance of the flows through the working fluid and the coolant has decreased which reduces energy costs for pumping media and creates favorable conditions for improving natural circulation. In this paper, the task is to analyze the features of the thermohydraulic characteristics of steam generator cassettes, to compare them with similar characteristics of coil steam generators in operation.

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Tieszen, S., H. Merte, V. S. Arpaci, and S. Selamoglu. "Crevice Boiling in Steam Generators." Journal of Heat Transfer 109, no. 3 (August 1, 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 surface. The results demonstrate the existence of three confinement-dependent boiling regimes in forced flow conditions that are similar to those found in pool boiling conditions. These regimes are shown to be associated with the Weber number.

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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 assuming elastic-perfectly plastic material behavior. For the crack location, both axial and circumferential surface cracks, and for each case, both external and internal cracks are considered. The resulting global and local limit load solutions are given in polynomial forms, and thus can be simply used in practical integrity assessment of the steam generator tubes, because the comparison between experimental data and FE solutions shows good agreement.

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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 (June 20, 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 energy flow streams to each auxiliary device and energy power consumption of each auxiliary device was also investigated throughout number steam system loads. Analysis of steam production from marine steam generators presented in this paper provides insight into the operation dynamics of the entire steam propulsion system.

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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 (December 20, 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. Based on the numerical results, fretting wear simulation is performed according to the environment to which the actual steam generators in nuclear power plant are exposed. Initial experimental results are obtained for various experimental parameters and the effect of work rate and temperature on fretting wear is evaluated.

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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 that result from nonhomogeneous thermal expansion of different parts of steam generator, etc.). The values of the strains caused by additional loads can sometimes exceed the value of the main strain. These can be decreased by the arrangement of additional supports or compensators or by changing the structure configuration. Sometimes, it is reasonable to increase the wall thickness of the calculated elements of the structures in order to reduce the strains caused by additional loads. Before getting to the strength computations for the assemblies and elements of the structures of steam generators we need to define first the character of the external loads on them (constant or cyclic load) and the deformability of their structural materials (ductile material, brittle material or limited plasticity material) and then to select the method for their strength computation. To provide a reliable operation of the steam generators of NPPs it is important to provide appropriate strength characteristics for all its assemblies and elements. These elements include process pipelines that are connected to the steam generator structure. These represent a spatially branched pipeline systems of a different technological purpose whose structures are supported by special fastening elements (the supports of different types, spring suspenders, etc.). The strength computations done for such systems include static and cyclic strength computations, seismic action computations, etc.

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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 (September 26, 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 circuit. At the same time, during the operation of the steam generator, deposits of corrosion products accumulate on the surface of the structural steel from the side of the 3rd circuit. The removal of deposits is carried out with the help of operational chemical flushes (ECPs). However, during the ECP, the corrosion rate of steel inevitably increases significantly (by about three orders of magnitude), which leads to an increase in the concentration of hydrogen in water and in sodium. This phenomenon has previously caused concern to the operational services of nuclear power plants due to the likely through-corrosion during regular ECP (every year, one of the three steam generators is washed). However, it is unacceptable to operate a steam generator without ECP, and to reduce the corrosion rate of steel of steam generator pipes in a steam-water environment, after ECP, a chemical passivation stage is carried out with different formulations, the effectiveness of which is different. This article presents a physical model of the mass transfer of corrosive hydrogen in a steam generator during chemical washing, passivation and start-up of the steam generator. An operational criterion for evaluating the effectiveness of passivation by the rate of increase in the concentration of hydrogen in the sodium of the second circuit during the subsequent start-up of BN-600 steam generators is proposed: if the rate of increase in the concentration of hydrogen in the 2nd circuit is less than 0.05 ppm/h, then passivation is effective, if more than the passivation formula requires revision. For BN-800 steam generators, the technology of passivation after ECP has not yet been determined, the article proposes a calculated criterion for its efficiency of 0.015 ppm/h.

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Rep, Ivan, Tomislav Tomašić, and Darko Barilar. "Sludge Deposit Mapping for Steam Generators." Journal of Energy - Energija 65, no. 1-2 (June 27, 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 of the inspected tube. Using automatic analysis deposit results are provided within 36 hours after the inspection. Results are imported in Sludge Mapping software and presented in 3D visualization of steam generator. Both PWR and VVER steam generator visualization is supported. Sludge mapping software provides visual information on sludge deposit thickness using color code and by calculation position of sludge indication, software draws the indication on the location within the steam generator where indication was found. Sludge mapping software provides information on heavy sludge loading areas of steam generator and can help with tracking of sludge build-up over time that can be used for optimizing steam generator maintenance. This paper presents INETEC’s Sludge Mapping solution, its functionality and features for visualization of sludge deposit location and thickness within the steam generator.

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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 generation unit. The steam generator is de-signed for operation on low grade coal - lignite with net calorific value 6280 to 9211 kJ/kg, in a cycle at 545?C/177.4 bar, with feed water temperature 251?C, combustion air preheated to 272?C and outlet flue gas temperature 160?C. Since the largest exergy dissipation in the thermal power plant cycle occurs in the steam generator, energy, and exergy balances of the furnace and heat exchanging surfaces are established in order to identify the main sources of inefficiency. On a basis of the analysis, optimization of the combustion and heat transfer processes can be achieved through a set of measures, including retrofitting option of lignite pre-drying with flue gas and air preheating with dryer exhaust gases.

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Egorov, Mikhail Yur’evich. "Vertical steam generators for VVER NPPs." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2018, no. 3 (September 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 (March 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 (January 1991): 31–42. http://dx.doi.org/10.1016/0306-4549(91)90035-v.

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Fennell, E., K. Kozminski, M. Bajpai, S. Easterday-McPadden, W. Elmore, C. Fromen, J. Gardell, 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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Au-Yang, M. K. "Flow-Induced Wear in Steam Generator Tubes—Prediction Versus Operational Experience." Journal of Pressure Vessel Technology 120, no. 2 (May 1, 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 material combinations and different support plate geometries became available. Based on the available data in the literature, as well as data obtained in the author’s affiliation, this paper assesses the cumulative tube wall wear after 5, 10, and 15 effective-full-power years of operation of a typical commercial nuclear steam generator, using different wear models. It is hoped that this study will shed some light on the probable mechanism that caused the observed wear in today’s operating nuclear steam generators.

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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 (March 21, 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 sample from both SG, one sample from each SG, etc.) does not affect the results of the inspection and also the information obtained about the state of the uninspected tubing, as long as the inspected steam generators belong to the same population. Numerical examples further demonstrate two possible states of the knowledge existing before the inspection of the tubing. First, virtually no knowledge about the state of the steam generator tubing before the inspection is modeled using uniform and triangular prior densities. It is shown that the knowledge about the uninspected part of the tubing strongly depends on the size of the sample inspected. Further, even small inspection samples may significantly improve our knowledge about the uninspected part. On the other hand, rather strong belief on the state of the tubing prior to the inspection is modeled using binomial prior density. In this case, the knowledge about the uninspected part of the tubing is virtually independent on the size of the sample. Furthermore, it is shown qualitatively and quantitatively that such inspection brings no additional knowledge on the uninspected part of the tubing.

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NISHIDA, Kenji, Hiroshi HIRANO, Toshiyuki MIZUTANI, and Yasuhiko HIRAO. "Conceptual Design of Steam Generator for IMR (Integrated Modular water Reactor) : Investigation of Tubular Steam Generators." Proceedings of the National Symposium on Power and Energy Systems 2002.8 (2002): 567–70. http://dx.doi.org/10.1299/jsmepes.2002.8.567.

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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 (July 1, 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 substantial financial benefit and helps offset overall operational costs. To achieve tangible financial gains, the mill must evaluate the overall cost of steam production and the price of electricity. The current work provides a case study of power plant optimization that evaluated electricity production and steam production costs balanced with mill steam demand. Process and cost optimization led to a significant reduction in low pressure steam venting, resulting in reduced fuel consumption and reduced operating cost.

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Arzhaev, Alexander, Alexey Arzhaev, Valentin Makhanev, Mikhail Antonov, Anton Emelianov, Aleksander Kalyutik, Yury Karyakin, 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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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 (October 31, 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 generator. To enhance the mass flow rate of vapor going into the ejector, a two-stage adjustable booster was added after the evaporator, which gives low evaporator temperature. A further experiment in which the two-stage adjustable booster was used before the generator to reduce the amount of work done by the generator. The ejector's cooling unit is powered by steam created from many energy sources powered by advanced hybrid heat and power systems, including solar energy and steam produced by the electric steam generator. The different devices are either directly triggered by a thermal source to achieve heating, cooling, or refrigeration. The steam boiler generator is the core of the cooling unit; in this research, various types of steam boiler generators are linked with adsorption units, such as steam-powered solar boilers, gas boilers, solid fuel steam boilers, and electric boilers. Heat exchangers were utilized to transfer heat from the solar chimney to the ejector cooling unit. The impact of various ejector geometries on the advanced cooling unit was studied and simulated for the single, double, and triple nozzle ejector. There were no issues with the more effective cooling unit. This unit performed better than traditional adsorption cooling units, having a greater efficiency.

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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 (November 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 method, adapted for the special conditions encountered in this kind of problem, allowing a considerable reduction of the computation time compared to other methods. Some emphasis is put on the modifications required to solve the equations for the evaporators because they are two-phase heat exchangers. A model for the steam drums is also presented together with simple models for the main control loops used in such systems. An example is presented in which an existing dual pressure level heat recovery steam generator is started from a cold state. The numerical predictions are in good agreement with measurements.

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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 (August 31, 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 and the development of empirical coefficients of gas movement inside the coaxial cylinders of the steam generator. In addition, another task is to develop a theoretical basis for the obtained experimental data. Based on the results of the work, the dependences of pressure and temperature on fuel consumption in various modes were obtained. Statistical analysis was applied to the data obtained. The authors have developed equations for calculating the convective part in the process of radiant-convective heat transfer in coaxial gas ducts, taking into account the design features of a once-through coil-type steam generator. Finally, promising directions for further improving the efficiency of steam generators of this type are proposed.

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Langston, Lee S. "Cogeneration: Gas Turbine Multitasking." Mechanical Engineering 134, no. 08 (August 1, 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 heat is used to generate up to 200,000 pounds per hour of steam in heat recovery steam generators (HRSGs). The HRSGs provide high-pressure steam to power a 4.6-MW steam turbine generator set for more electrical power and low-pressure steam for campus heating. The waste heat from the steam turbine contained in low-pressure turbine exhaust steam is combined with the HRSG low-pressure steam output for campus heating.

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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 (March 19, 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 volatilization and transfer into the steam phase. During unstable evaporation in the steam generators an extensive physical carryover of alloying metal species was observed. At realistic operation conditions for steam electrolysis, the gas preheater caused a considerable release of silicon into the steam phase. Two stack experiments were performed with common preheater temperatures and showed largely increased cell voltage degradation at higher operation temperatures. The post-test chemical analysis of cell samples revealed significant concentrations of silicon in the samples that are regarded as primary cause for increased degradation. These findings could partially explain the wide spread of degradation rates reported for solid-oxide steam electrolysis experiments.

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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 (June 1, 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 implement a water level controller for steam generators based on a fuzzy model predictive control approach. An original concept of modular evolved control system, seamless and with gradual integration into the existent control system is proposed as base of implementation of the presented system.

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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 (April 1, 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 gas turbine exhaust flow is run in parallel with a conventional heat recovery steam generator (HRSG). This side stream is supplementary fired opposed to the current practice of full exhaust flow firing. Chemical fuel gas recuperation can be incorporated in the side stream as an option. A significant combined cycle efficiency gain of 2 to 4 percentage points can be realized using this split stream approach. Calculations and graphs show how the DOE goal of 60 percent combined cycle efficiency burning natural gas fuel can be exceeded. The boiler concept is equally applicable to the integrated coal gas fuel combined cycle (IGCC).

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35

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 (December 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 in the article and the same have to be avoided in order to assure a reliable life span of the low duty compressor and smooth operation of the main steam generators. Furthermore, for preventing efficiency losses of a steam power plant, some methods for avoiding surge effects are emphasized and recommended.

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36

Suresh Kumar, V. A., I. B. Noushad, and K. K. Rajan. "Steam generator test facility—A test bed for steam generators of Indian sodium cooled fast breeder reactors." Nuclear Engineering and Design 248 (July 2012): 169–77. http://dx.doi.org/10.1016/j.nucengdes.2012.03.021.

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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 (October 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 primary measuring transducers and the control mechanisms of the experimental stand are described. The choice of the configuration of the automated control and measurement system is justified from the point of view of completeness and reliability of the obtained data.

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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 (October 1, 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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Rodríguez, Martín A. "Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: a review." Corrosion Reviews 38, no. 3 (June 4, 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 and other components of the secondary cooling system from corrosion during plant outages.

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40

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 generator tube to facilitate temperature measurement at or near to the locations of interest. The modified steam generator tube will be sealed at the feed header upstand. Between the upper surface of the superheater header tubeplate and the wall of the superheater header, the thermocouple bundle and sheath will be contained within a rigid stainless steel guide tube. The guide tube will be attached at both ends by welds, each forming a pressure boundary. At the tubeplate a weld will separate the bore of the sealed guide tube from the steam space within the superheater header; a weld between the guide tube and the superheater header will separate the steam space within the superheater header from atmosphere outside the header. In order to obtain a better design, three 3-dimentional finite element models have been created using ABAQUS. A series of cyclic pressure, and start-up and shutdown thermal transient stress analyses have been carried out to provide stress values for structural integrity assessments to be conducted using ASME III, Subsection NH and R5.

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41

Ueno, Takashi, Ayao Tsuge, Kohei Kawanishi, Tatsuya Ochi, and Ei Kadokami. "Advanced Boron Soaking Procedure for Steam Generators." JSME International Journal Series B 36, no. 3 (1993): 449–55. http://dx.doi.org/10.1299/jsmeb.36.449.

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Mitra, T. K., Aravinda Pai, and Prabhat Kumar. "Challenges in Manufacture of PFBR Steam Generators." Energy Procedia 7 (2011): 317–22. http://dx.doi.org/10.1016/j.egypro.2011.06.041.

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Nandakumar, R., S. Athmalingam, V. Balasubramaniyan, and S. C. Chetal. "Steam Generators for Future Fast Breeder Reactors." Energy Procedia 7 (2011): 351–58. http://dx.doi.org/10.1016/j.egypro.2011.06.046.

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Elter, C., and R. Franke. "Gas pressure test of THTR steam generators." International Journal of Pressure Vessels and Piping 24, no. 1 (January 1986): 37–48. http://dx.doi.org/10.1016/0308-0161(86)90029-3.

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Birks, A. S., S. D. Brown, A. E. Curtis, and C. S. Welty. "US developments in NDE for steam generators." International Journal of Pressure Vessels and Piping 28, no. 1-5 (January 1987): 203–7. http://dx.doi.org/10.1016/0308-0161(87)90076-7.

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Gray, B. S. "European developments in NDE for steam generators." International Journal of Pressure Vessels and Piping 28, no. 1-5 (January 1987): 209–17. http://dx.doi.org/10.1016/0308-0161(87)90077-9.

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Budov, V. M., S. A. Zamyatin, V. A. Farafonov, and V. I. Churyumov. "Operating temperatures in coiled-tube steam generators." Soviet Atomic Energy 67, no. 1 (July 1989): 527–30. http://dx.doi.org/10.1007/bf01126394.

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48

Habibiyan, H., A. Sayadian, and H. Ghafoori-Fard. "Wavelet network controller for nuclear steam generators." Journal of Physics: Conference Series 23 (January 1, 2005): 182–91. http://dx.doi.org/10.1088/1742-6596/23/1/020.

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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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Liu, Jie, Qinglei Liu, Dongling Ma, Yang Yuan, Jiahao Yao, Wang Zhang, Huilan Su, Yishi Su, Jiajun Gu, and Di Zhang. "Simultaneously achieving thermal insulation and rapid water transport in sugarcane stems for efficient solar steam generation." Journal of Materials Chemistry A 7, no. 15 (2019): 9034–39. http://dx.doi.org/10.1039/c9ta00843h.

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Journal articles on the topic 'Steam generators'

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