Relevant bibliographies by topics / Draft loss of steam generator

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

Academic literature on the topic 'Draft loss of steam generator'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Draft loss of steam generator"

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Luo, Run, Chunyu Liu, and Rafael Macián-Juan. "Investigation of Control Characteristics for a Molten Salt Reactor Plant under Normal and Accident Conditions." Energies 14, no. 17 (August 25, 2021): 5279. http://dx.doi.org/10.3390/en14175279.

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A molten salt reactor (MSR) has unique safety and economic advantages due to the liquid fluoride salt adopted as the reactor fuel and heat carrier fluid. The operation scheme and control strategy of the MSR plant are significantly different from those of traditional solid-fuel reactors because of the delayed neutron precursors drift with the liquid-fuel flow. In this paper, a simulation platform of the MSR plant is developed to study the control characteristics under normal and accident conditions. A nonlinear dynamic model of the whole system is built in the platform consisting of a liquid-fuel reactor with a graphite moderator, an intermediate heat exchanger and a steam generator. A new control strategy is presented based on a feed-forward and feedback combined scheme, a power control system and a steam temperature control system are designed to regulate load changes of the plant. Three different types of operation conditions are simulated with the control systems, including transients of normal load-follow operation, a reactivity insertion accident and a loss of flow accident. The simulation results show that the developed control system not only has a fast load-follow capability during normal operation, but also has a good control performance under accident conditions.
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Xu, Qi Sheng, Xiao Wei Peng, Jie Wu, Xiao Qian Ma, Yue Xi Yu, and Zhi Bin Xu. "Economic and Environmental Analysis for Steam-Driven Induced Draft Fans of 1036MW Ultra Supercritical Units." Advanced Materials Research 787 (September 2013): 553–57. http://dx.doi.org/10.4028/www.scientific.net/amr.787.553.

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Concerning the steam induced draft fan renovation tendency in large coal-fired power plants, the economic and environmental benefit are analysed for certain 1036MW ultra supercritical units. Under the same generator output, despite the power generation coal consumption for the scheme with steam induced draft fan coal increased, the auxiliary power reduced significantly which results in roughly RMB 10,657 thousands yuan economic saving every year with about 1.9 years payback period of investment. Due to the power supply coal consumption saving, the annual amount of pollutants reduction of CO2, SO2, NO2 and dust are 4440.867, 16.462, 45.514 and 220.829t, respectively.
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Huang, Yuchen, Lin Chen, Xianwei Huang, Xiaoze Du, and Lijun Yang. "Performance of natural draft hybrid cooling system of large scale steam turbine generator unit." Applied Thermal Engineering 122 (July 2017): 227–44. http://dx.doi.org/10.1016/j.applthermaleng.2017.04.120.

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Wei, Yaobing, Xin Wang, Yuanyuan Kong, and Changfeng Yan. "A probability uncertainty method of fault classification for steam turbine generator set based on Bayes and Holospectrum." Proceedings of the Institution of Mechanical Engineers, Part C: Journal of Mechanical Engineering Science 230, no. 20 (August 9, 2016): 3767–76. http://dx.doi.org/10.1177/0954406215616146.

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With the rapid development of the machinery and the increasing complexity of the steam turbine generator set, it is a great challenge for the safe and reliable operation of the steam turbine generator set. The uncertainties of fault classification and complicated working conditions become important research fields of steam turbine generator. A probability method on the uncertainty reasoning of fault classification for steam turbine generator is proposed in this paper based on the 2D-holospectrum and Bayesian decision theory. Firstly, Bayesian decision theory is adopted for the preliminary fault estimation on actual risk loss by calculating the loss expectation of each decision. Then, the area ratio of overlap region in 2D-holospectrum and the evidence theory can give the probability of the fault. Framework and model of the uncertainty reasoning are also described in this paper. Finally, the model is verified by the experiment of the rotor vibration on test rig. The results show that the method proposed is feasible for reasoning under imperfect information condition.
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Zhang, Li Na, Hui Zhao, and Min Shan Liu. "Research on Fluid-Structure Interaction Dynamic Characteristics of Steam Generator Heat Exchanger Tubes." Advanced Materials Research 482-484 (February 2012): 183–87. http://dx.doi.org/10.4028/www.scientific.net/amr.482-484.183.

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For heat exchanger tube of steam generator, the relation between heat exchanger tube and fluid is typical fluid-structure interaction problem. Flow induced vibration has been found so far to be responsible for fatigue damage and failure of steam generator tubes, which will result in large economic loss and radioactive pollution. So the steam generator tubes are the weakest link in the primary coolant loop. Based on the synthesis of all sorts of factors influencing the dynamic characteristics of steam generator heat transfer tubes, establishing the heat transfer tube model, research on the weakening effect of fluid hole on fluid, the natural frequencies of the heat transfer tubes are analyzed under different fluid holes and fluid hole distance by numerical simulation.
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Kocijel, Lino, Igor Poljak, Vedran Mrzljak, and Zlatan Car. "Energy Loss Analysis at the Gland Seals of a Marine Turbo-Generator Steam Turbine." Tehnički glasnik 14, no. 1 (March 20, 2020): 19–26. http://dx.doi.org/10.31803/tg-20191031094436.

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The paper presents an analysis of marine Turbo-Generator Steam Turbine (TGST) energy losses at turbine gland seals. The analyzed TGST is one of two identical Turbo-Generator Steam Turbines mounted in the steam propulsion plant of a commercial LNG carrier. Research is based on the TGST measurement data obtained during exploitation at three different loads. The turbine front gland seal is the most important element which defines TGST operating parameters, energy losses and energy efficiencies. The front gland seal should have as many chambers as possible in order to minimize the leaked steam mass flow rate, which will result in a turbine energy losses’ decrease and in an increase in energy efficiency. The steam mass flow rate leakage through the TGST rear gland seal has a low or negligible influence on turbine operating parameters, energy losses and energy efficiencies. The highest turbine energy efficiencies are noted at a high load – on which TGST operation is preferable.
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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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Song, Changyuan, Xuying Chen, Rui Hao, Dongna Cai, Xiangwei Zhu, Hao Liu, Jinzhou Chen, and Wentao Liu. "A cocoon-based 3D solar steam generator for high-performance saline water desalination." Sustainable Energy & Fuels 5, no. 16 (2021): 4126–32. http://dx.doi.org/10.1039/d1se00708d.

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Mrzljak, Vedran, Paolo Blecich, Nikola Anđelić, and Ivan Lorencin. "Energy and Exergy Analyses of Forced Draft Fan for Marine Steam Propulsion System during Load Change." Journal of Marine Science and Engineering 7, no. 11 (October 28, 2019): 381. http://dx.doi.org/10.3390/jmse7110381.

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A forced draft fan, used for the supply of combustion air into the steam generator of the conventional liquefied natural gas (LNG) carrier was analyzed from the aspect of energy and exergy. The power delivered from the induction motor to the fan was calculated using the manufacturer’s data. The most significant impact on the fan energy power losses is from the air temperature difference between the fan outlet and inlet. The fan energy power losses are inversely proportional to the fan energy efficiency, and the values are between 19.9% and 63.4%, for the entire range of observed steam system loads. The fan exergy destruction depends primarily on the driving power and on the air mass flow rate. At higher loads, an important influence on the fan exergy destruction is from the air pressure at the fan outlet. The exergy efficiency change of the analyzed fan, for the range of observed steam system loads, is directly proportional to the rate of change in the air mass flow, whereas the obtained values of exergy efficiency are between 5.10% and 53.93%. The impact of ambient temperature on the fan exergy destruction and exergy efficiency exhibits is different than in most other steam system components. A change in ambient temperature of 10 °C causes a change in the exergy efficiency of the forced draft fan less than 0.5% in the entire range of observed steam loads.
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Jin, H., M. Ishida, M. Kobayashi, and M. Nunokawa. "Exergy Evaluation of Two Current Advanced Power Plants: Supercritical Steam Turbine and Combined Cycle." Journal of Energy Resources Technology 119, no. 4 (December 1, 1997): 250–56. http://dx.doi.org/10.1115/1.2794998.

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Two operating advanced power plants, a supercritical steam plant and a gas-steam turbine combined cycle, have been analyzed using a methodology of graphical exergy analysis (EUDs). The comparison of two plants, which may provide the detailed information on internal phenomena, points out several inefficient segments in the combined cycle plant: higher exergy loss caused by mixing in the combustor, higher exergy waste from the heat recovery steam generator, and higher exergy loss by inefficiency in the power section, especially in the steam turbine. On the basis of these fundamental features of each plant, we recommend several schemes for improving the thermal efficiency of current advanced power plants.
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Dissertations / Theses on the topic "Draft loss of steam generator"

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Ptáček, Ondřej. "Návrh dvoutlakého vertikálního kotle na odpadní teplo za plynovou turbínou na zemní plyn." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2017. http://www.nusl.cz/ntk/nusl-319246.

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This diploma thesis deals with proposal of a two-lane vertical boiler using the waste heat after gas turbine. In the first part the heat calculation has been done followed by the arrangement of particular heat exchange surfaces and the drawing of real saw diagram. There are also dimensions of drums, inlet and outlet pipes and transfer pipelines drafted. Furthermore, I have listed the materials that are used for casing the boiler and pipelines. Finally, the boiler loss is calculated and the boiler hydraulic calculation is performed. The supplement contains a boiler drawing.
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Maršík, Jaroslav. "Dvoutlaký horizontální kotel na odpadní teplo (HRSG)." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2015. http://www.nusl.cz/ntk/nusl-232157.

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The Master’s thesis dealing with design of heat recovery steam generator with two pressure levels is split into nine sections. The first section describes the design and the layout of HRSG. The second part deals with heat calculation. The third section deals with design of flue-gas duct. The fourth part describes designs of individual heating surfaces, including steam superheaters, vaporizers and economizer. Next section shows the real temperature diagram and choice of the materials. The seventh section describes the calculation of outer pipelines and the eighth part deals with the drums design. The last section deals with the calculation of draft loss of steam generator.
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Slíva, Karel. "Návrh dvoutlakého horizontálního kotle na odpadní teplo." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2016. http://www.nusl.cz/ntk/nusl-254297.

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The focus of this thesis is a proposal of a horizontal dual-pressure heat recovery steam generator. The introductory part includes thermal calculation, as well as a design of the layout and a design of the heat transfer surfaces and the layout of the boiler. Individual chapters are broken down according to the outline of the proposal for the arrangement of the heating surfaces, according to the parameters of the flue gas and steam. The master thesis contains a scheme of a real heat transfer temperature diagram and it also includes the calculation of connecting and downcomer pipes and drums. The final part describes the calculation of the boiler draft loss. The main idea of the thesis is accompanied by the technical documentation of the drawing of the boiler.
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Med, Lukáš. "Návrh dvoutlakého horizontálního kotle na odpadní teplo." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2016. http://www.nusl.cz/ntk/nusl-241924.

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This master's thesis deals with thermal calculation and design of proportions of calorific components of a heat recovery steam generator (HRSG), which is placed behind a combustion turbine, for given parameters of exhaust gases and requested parameters of steam. In the first chapters is described the design, layout of HRSG and the thermal calculation. The next parts deal with the design of flue-gas duct and each individual heating surface. Next section shows computations of dimensions of drums, flooding pipes, transferring pipes and all other outer pipes. The chosen materials are described in one of the last chapters and the last chapter deals with calculation of draft loss of steam generator.
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Kamboj, Brij Kumar. "Modeling of once-through steam generator thermal-hydraulics during a loss of coolant accident." Diss., Georgia Institute of Technology, 1993. http://hdl.handle.net/1853/16660.

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Sethapati, Vivek Venkata. "Computational Fluid Flow Analysis of the Enhanced-Once through Steam generator Auxiliary feedwater system." Thesis, Virginia Tech, 2011. http://hdl.handle.net/10919/77020.

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The once through steam generator (OTSG) is a single pass counter flow heat exchanger in which primary pressurized water from the core is circulated. Main Feedwater is injected in an annular gap on the outer periphery of the steam generator shroud such that it aspirates steam to preheat the feedwater to saturation temperature. An important component of the OTSG and enhanced once through steam generator (EOTSG) is the auxiliary feedwater system (AFW), which is used during accident/transient scenarios to remove residual heat by injecting water through jets along the outer periphery of the heat exchanger core directly on to the tubes at the top of the OTSG. The intention is for the injected water, which is subcooled, to spread into the tube nest and wet as many tubes as possible. In this project, the main objectives were to use first principles Computational Fluid Dynamics to predict the number of wetted tubes versus flow rate in the EOTSG at the AFW injection location above the top tube support plate. To perform the fluid analysis, the losses in the bypass leakage flow and broached hole leakage flow were first quantified and then used to model a 1/8th sector of the EOTSG. Using user defined functions (UDF), the loss coefficients of the leakage flows were implemented on the 1/8th sector of the EOTSG computational model to provide boundary conditions at the bypass flow and leakage flow locations With this method, the number of tubes wetted in the sector of EOTSG for various AFW flow rates was found. Results showed that the number of wetted tubes was in very close agreement to that predicted by experimental-analytical methods by the sponsor, AREVA. With the maximum flow rate of 65 l/s a total of 318 tubes were wetted and the percentage of tubes wetted with broached holes was 8.7%. The analysis on the bypass leakage flow showed that the loss coefficients was a function of the mass flow rate or the flow Reynolds number through the gap and it increased as the Reynolds number increased from 300 to 1600. The experimental and computational loss coefficients agree to within 15% of each other. In contrast, the constant loss coefficient of 1.3 used by AREVA was much higher than that obtained in this study, particularly in the low Reynolds number range. As the Reynolds number approached 3000, the loss coefficients from this study approached the value of 1.3. This value of the loss coefficient was implemented for the bypass flow leakage in the 1/8th sector of the EOTSG model. The analysis on the broached hole leakage flow was performed using a single hole, five holes, and one, two, four and eight rows of broached holes in order to characterize the loss coefficients. The one hole and five hole computational models were validated with experiments. The computational models showed the presence of voids in the leakage flow through the tube support plate (TSP), which were not observed (visually) in the experiments. The characterization of the broached hole leakage in the one, two and four rows showed that the loss coefficient of the control broached hole increased as the number of rows increased. These results indicated that for the same height of water on the TSP, the resistance to leakage flow increased as the number of tubes increased. They also indicated that leakage flow through the broached holes was not solely a function of the height of water above the TSP but also the surrounding geometrical topology and the flow characteristics. However, the analysis done for eight rows showed that the loss coefficient became constant after a certain number of rows as the loss coefficient differed by only 5% from the results of the four rows. From these results it was determined that the loss coefficient asymptotes to an estimated value of 4.0 which was implemented in the broached hole leakage flow in the 1/8th sector of the EOTSG. Computational models of the 1/8th sector of the EOTSG were implemented with the respective loss coefficients for the bypass and leakage flows. Results showed that as the AFW flow rate increased, the percentage wetted tubes increased. The data matched closely with AREVA's experimental-analytical model for flow rates of 14.5 l/s and higher. It was also deduced that complete wetting of the tubes is not possible at the maximum AFW flow rate of 65 l/s.
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Books on the topic "Draft loss of steam generator"

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Mendler, O. J. Loss of feed flow, steam generator tube rupture, and steam line break thermohydraulic experiments: MB-2 steam generator transient response test program. Washington, DC: U.S. Nuclear Regulatory Commission, 1986.

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Mendler, O. J. Loss of feed flow, steam generator tube rupture, and steam line break thermohydraulic experiments: MB-2 steam generator transient response test program. Washington, DC: U.S. Nuclear Regulatory Commission, 1986.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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Voltage-based interim plugging criteria for steam generator tubes: Draft report for comment. Washington, DC: U.S. Nuclear Regulatory Commission, 1993.

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10

E, Wilson G., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., and Idaho National Engineering and Environmental Laboratory., eds. Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios. 2nd ed. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

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Book chapters on the topic "Draft loss of steam generator"

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Joseph Winston, S., Joel Jose, D. Jagadishan, S. Sakthivel, P. Visweswaran, S. Murugan, G. Amarendra, and P. V. Manivannan. "Degenerated Degree of Freedom Sensing Without Loss of Accuracy While Estimating the Rigid Body Parameters for the Calibration of a Two-Axis Robotic Arm for Prototype Fast Breeder Reactor, Steam Generator Inspection System." In Lecture Notes in Mechanical Engineering, 619–35. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-8597-0_53.

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Conference papers on the topic "Draft loss of steam generator"

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Smith, Raub W. "Achieving Better Power Plant Guarantees Through a New Exergy-Based Approach for the HRSG." In ASME Turbo Expo 2021: Turbomachinery Technical Conference and Exposition. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/gt2021-59291.

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Abstract The best assurance an owner has to maximize the performance of the entire combined cycle power plant is perfect alignment of HRSG performance guarantee metrics to this goal. Currently, HRSG equipment performance guarantees include steam generation rates and steam temperature at each pressure level plus draft loss and reheater pressure drop. This profusion of guaranteed parameters with multiple bonus/LD rates is not always well correlated to the customer’s ultimate goal of delivering MW from the bottoming cycle since the behavior of each steam generation circuit is a complex function of steam pressure, steam turbine performance, and GT exhaust temperature. This paper proposes a solution that normalizes and combines all HRSG performance measurements into a single value directly and reliably tied to the customer value metric (which may be different for fired and unfired operation or other load points). This is achieved by expressing the HRSG performance guarantee in terms of exergy recovered to steam and plant exergy loss attributable to the HRSG (gas side draft loss). This will be shown, with examples, to serve the goals of the customer to confirm by test that an HRSG delivers the promised steam exergy consistent with the plant level performance requirement.
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Kinoshita, Ikuo, Toshihide Torige, and Minoru Yamada. "Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry." In ASME 2014 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/imece2014-38114.

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An application of the Best Estimate Plus Uncertainty (BEPU) method is made to an analysis of the “Intentional depressurizaion of steam generator secondary side” which is an accident management procedure in a small-break loss-of-coolant accident (SBLOCA) with high pressure injection (HPI) system failure. RELAP5/MOD3.2 is used as the system analysis code. Interfacial friction in the core affects the two-phase mixture level and the distribution of the dispersed gas phase. This phenomenon is very important in terms of the influence its uncertainty has on the peak cladding temperature. The RELAP5/MOD3.2 code uses drift-velocity to describe the interfacial friction coefficients in vertical dispersed flow. The Chexal-Lellouche drift-flux correlation is used for the rod bundle geometry. In the present study, the RELAP5 model uncertainty was quantified regarding the interfacial friction coefficients in the rod bundle geometry by conducting numerical analyses of separate effect tests. As the separate effect tests, two-phase mixture level swell tests in the Thermal Hydraulic Test Facility (THTF) of the Oak Ridge National Laboratory (ORNL) were used. After considering applicability to the SBLOCA, tests were selected for which conditions of pressures and rod powers were similar to PWR plant conditions. A total of 55 data were used. The model uncertainty parameter was defined as a multiplier for the interfacial friction coefficient. Numerical analyses were performed by adjusting the multiplier so that the predicted void fractions agreed with the experimental measured data. The resultant distribution of the multipliers represented the model uncertainty. The mean, standard deviation, minimum and maximum values of this uncertainty distribution were 0.88, 0.55, 0.13 and 3.0, respectively.
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Lu, Jianan, Jiong Guo, and Fu Li. "Accurate Simulation of HTGR Steam Generator for Pressurized Loss of Forced Cooling Accident." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60333.

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Nuclear power plant is a large-scale complicated system, which includes reactor core, steam generator, turbine and other important components. These components are tightly coupled with each other. Among these components, steam generator is the key link of primary circuit system and secondary circuit system. Heat transfers from primary side to secondary side. Once-through steam generator applied in high temperature gas cooled reactor (HTGR) has the properties of small heat capacity and rapid response speed. In HTGR system, the steam generator should match with the properties of reactor core such as large heat capacity and the slow response. Therefore, accurately simulating the steam generator is a complex task and has a great impact on the coupling property of a reactor system. To address this issue, effects of boundary conditions on the output water quality are analyzed and time integration schemes of backward differentiation formula (BDF) are implemented to HTGR steam generator simulation code BLAST in this work. The introduced BDF is a higher-order approximation to a transient term. It can reduce the numerical error from an explicit time integration scheme. The modified code is numerical tested in a noteworthy HTGR accident operation condition: Pressurized Loss Of Forced Cooling (PLOFC) accident. The performance of HTGR steam generator in the accident is analyzed. The accuracy of the improved algorithm is compared with the original BLAST code. Result shows the safety characteristics of steam generator in PLOFC accident and indicates that the numerical accuracy is significantly improved for both helium and water sides by BDF. For the consideration of accuracy and stability, BDF2 is chosen in the modified BLAST code.
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Marra, Dominic. "Optimizing Steam Turbine Generator Output: Identifying Opportunities." In 13th Annual North American Waste-to-Energy Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/nawtec13-3164.

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In an effort to maximize steam turbine generator output, Montenay Power Corp. (MPC), operator of the Miami Dade County Resources Recovery Facility (DCRRF) undertook a systematic approach to analyze various turbine and steam cycle issues affecting performance. Several low cost methods were used to identify opportunities for increased megawatt generation. Shortfalls within the actual steam path through the turbine blading and internals were quantified with a steam path audit and computerized modeling of the blade path. This audit identified a shortfall of 2.5 megawatts (MW) from the original design and almost a full 1 MW gain through work done during the regular maintenance overhaul. The audit proved to be a valuable tool for making good economic decisions on what seal packing to replace/repair during the TG overhaul. The plant had previously explored re-blading options with the Original Equipment Manufacturer (OEM). This brief study showed turbine internal changes would be capital intensive and carry megawatt improvement claims that were questionable due to various steam cycle issues. Four major operational parameters that affect turbine performance were examined and quantified. Deviations from design steam flow, throttle temperature, back pressure, and throttle pressure accounted for a loss of 24 megawatts (MW) in generation. The three low cost methods used to quantify these losses/opportunities were: 1) Acoustic valve leak detection surveys which identified not only low cost MW gain improvement opportunities but also safety and reliability issues; 2) Helium tracer gas leak detection, used to identify vacuum leaks and confirm the leaks were sealed properly; and 3) A complimentary steam trap survey, which also helped identify lost steam and potential risk to equipment. Preliminary measures were taken to improve steam throttle flow, throttle temperature, back pressure and throttle pressure with a net gain of 7 MW so far. This paper details the methods used and results of the optimization program thus far.
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Kumar, Rajeev, and Onkar Singh. "Computer Simulation and Optimization of Heat Recovery Steam Generator (HRSG)." In ASME Turbo Expo 2003, collocated with the 2003 International Joint Power Generation Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/gt2003-38095.

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Heat recovery steam generators are successfully used in combined cycle power plants and many more applications. In a gas / steam combined cycle power plant the performance of bottoming cycle depends largely upon the effectiveness of HRSG. For a good HRSG in combined cycle power plants the heat exchange effectiveness should be as high as possible for maximum waste heat utilization and loss in the pressure of hot gases passing through HRSG should be small. In this paper, the computer simulation of HRSG has been carried out based on its thermodynamic study. An exhaustive generic computer code has been developed in C++ language for getting the critical information such as surface area required, number of tubes required, pressure loss, steam generation rate, effectiveness etc. for a single pressure & multi pressure HRSG. Results obtained using the code have been analyzed for varying operating thermodynamic conditions and different arrangements in HRSG. Preferable HRSG configuration and its thermodynamic analysis have been made using the computer code. Optimization of the HRSG design is carried out in respect to cost of HRSG using genetic algorithm.
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Cinotti, L., M. Bruzzone, N. Meda, G. Corsini, C. V. Lombardi, M. Ricotti, and L. E. Conway. "Steam Generator of the International Reactor Innovative and Secure." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22570.

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IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral reactor vessel that contains all the main reactor coolant system components including the reactor core, the coolant pumps, the steam generators and the pressurizer. This integral design approach eliminates the large coolant loop piping, and thus eliminates large loss-of-coolant accidents (LOCAs) as well as the individual component pressure vessels and supports. In addition, IRIS is being designed with a long-life core and enhanced safety to address the requirements defined by the US DOE for Generation IV reactors. The design of the steam generators, which are internally contained within the reactor vessel, is a major design effort in the development of the integral IRIS concept. The ongoing design activity about the steam generator is the subject of this paper.
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7

Jin, Hugh. "A Study of Coal-Fired Steam Generator Efficiencies." In ASME 2011 Power Conference collocated with JSME ICOPE 2011. ASMEDC, 2011. http://dx.doi.org/10.1115/power2011-55137.

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ASME Performance Test Code PTC 4 for “Fired Steam Generators” superseded previous Code PTC 4.1 in 1998[1][2]. PTC 4 corrects many of the deficiencies in PTC 4.1 and makes testing more accurate and easy to integrate into plant performance tests. PTC 4.1 however continues to be used in many parts of the industry mainly due to its simplicity and ease of use. The use of both PTC 4 and PTC 4.1 has caused confusion. Direct comparison of testing results obtained in accordance with the two Codes may lead to wrong conclusions. Fundamentally, PTC 4 is a more technically sound and comprehensive Code than PTC 4.1 was. The calculation procedures of PTC 4 are intended to produce more accurate loss results and reduce the uncertainty. For example, the surface radiation and convection losses are measured instead of estimated, and the un-measured minor losses must be estimated individually if not measured, with appropriate uncertainty values. Therefore, the level of uncertainty associated with the estimate of unmeasured losses commonly assumed by a lump sum value in PTC 4.1 would normally be greater than that associated with the individually estimated losses by PTC 4. This paper presents a study of steam generator efficiency and fuel flow for a 700MW net coal-fired power plant with the application of both PTC 4 and PTC 4.1 Codes. Without considering the differences in uncertainty analysis, radiation / convection losses, and un-measured losses / credits, it is found that the results of tests conducted by the two methods vary marginally, given that the gross efficiency in the scope of PTC 4.1 is converted into the fuel efficiency as defined by PTC 4. The difference between the PTC 4 and 4.1 efficiencies is principally due to the energy credits associated with auxiliary equipment power consumption. The paper also discusses differences in efficiency definitions, efficiency conversions, and fuel flow calculations between the two Codes.
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8

Vadlamani, Ram Anand, Shripad T. Revankar, and Jovica R. Riznic. "Choking Flow of Subcooled Liquid in Steam Generator Tube Wall Cracks." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30256.

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Steam generator tubes have a history of small cracks and even ruptures, which lead to a loss of coolant from the primary side to the secondary side. Currently, steam generators operate under a leak-before-break approach. A rupture then signifies the loss of the integrity of the tube itself. Therefore, choking flow plays an integral part not only in the engineered safeguards of a nuclear power plant, but also to everyday operation. Choked flow of subcooled water through small cracks such as in steam generator tube wall cracks is studied both with experiments and analytical models. The knowledge of this maximum flow rate through a crack in the steam generator tubes of a pressurized water nuclear reactor will allow designers to calculate leak rates and design inventory levels accordingly while limiting losses during loss of coolant accidents. Slits of very small channel length to hydraulics diameter ratio (L/D) were manufactured and tested upto 6.89 MPa pressure and range of subcoolings 10–40 °C. Small flow channel length was used (1.3mm) equivalent to steam generator tube thickness with differences in surface roughness. The effect of L/D on the choking flow rates was examined and was contrasted with other data in literature. Analytical models were applied highlighting the importance of non-equilibrium effects and the effects of L/D ranging from 1.3 to 400 on the chocked flow were investigated.
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9

Brunin, Olivier, Geoffrey Deotto, Franck David, Joe¨l Pillet, Gilles Dague, and Alexandre Nicoli. "Measurement of Pressure Loss Throughout a Clogged Steam Generator Tube Support Plate in Single Phase Flow." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25606.

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After a period of several years of operation, steam generators can be affected by fouling and clogging. Fouling means that deposits of sludge accumulate on tubes or tube support plates (TSP). That results in a reduction of heat exchange capabilities and can be modelled by means of a fouling factor. Clogging is a reduction of flow free area due to an accumulation of sludge in the space between TSP and tubes. The increase of the clogging ratio results in an increase of the overall TSP pressure loss coefficient. The link between the clogging ratio and the overall TSP pressure loss coefficient is the most important aspect of our capability to accurately calculate the thermal-hydraulics of clogged steam generators. The aim of the paper is to detail the experimental approach chosen by EDF and AREVA NP to address the calculation uncertainties. The calculation method is classically based on the computation of a single-phase (liquid-only) pressure loss coefficient, which is multiplied by a two-phase flow factor. Both parameters are well documented and can be derived on the basis of state of the art methods such as IDEL’CIK diagrams and CHISHOLM formula. The experimental approach consists of a validation of the correlations by performing tests on a mock-up section with an upward flow throughout a vertical array of tubes. A mixture of water and vapour refrigerant R116 is used to represent two-phase flows. The tube bundle is composed of a 25 tubes array in a square arrangement. The overall height of the mock-up is 2 m. Eight test TSPs were manufactured, considering eight different clogging configurations: six plates with a typical clogging profile at six clogging ratios (0, 44%, 58%, 72%, 86%, 95%), and two plates with a clogging ratio of 72% associated with two different clogging profiles (large bending radius profile and rectangular profile). A series of tests were performed in 2009 in single-phase flow conditions. Two-phase flow tests with a mixture of liquid water and vapour refrigerant R116 will be performed in 2010. The paper illustrates the main results obtained during the single-phase tests performed in 2009.
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10

Hamouda, Ouajih, David S. Weaver, and Jovica Riznic. "An Experimental Study of Steam Generator Tube Loading During Blowdown." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-45250.

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If the main steam line from a nuclear steam generator were to break, the water in the steam generator would rapidly flash off in what is called a blowdown. Such an event could produce significant loading on the steam generator tubes, which if fractured, could lead to a loss of radioactive materials from containment. Thus, knowing the tube loading during such an event is an important input for safe design. This paper presents the results of an experimental laboratory study of the transient tube loading during a simulated blowdown. The working fluid was R-134a and the sectional tube model was a normal triangular array with a pitch ratio of 1.36. Tests were conducted with various levels of liquid R-134a and various numbers of tube rows. The transient tube loading is explained in terms of the associated flow physics and the maximum load is compared with existing models for tube loading obtained under steady flow conditions.
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Reports on the topic "Draft loss of steam generator"

1

Mendler, O., K. Takeuchi, and M. Young. Loss of feed flow, steam generator tube rupture and steam line break thermohydraulic experiments. Office of Scientific and Technical Information (OSTI), October 1986. http://dx.doi.org/10.2172/5088258.

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2

Wilson, G. E., C. D. Fletcher, and C. B. Davis. Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios. Office of Scientific and Technical Information (OSTI), June 1997. http://dx.doi.org/10.2172/501518.

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