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Journal articles on the topic 'Pressurized steam'

Author: Grafiati

Published: 4 June 2021

Last updated: 7 February 2022

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1

Sinha, Dr Deepa A., and Digant Dave. "Experimental Analysis on Behavior of Concrete Under High Temperature Pressurized Steam." Indian Journal of Applied Research 4, no. 7 (2011): 212–15. http://dx.doi.org/10.15373/2249555x/july2014/65.

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2

Jariyaboon, M., P. Møller, and R. Ambat. "Effect of pressurized steam on AA1050 aluminium." Anti-Corrosion Methods and Materials 59, no. 3 (2012): 103–9. http://dx.doi.org/10.1108/00035591211224645.

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3

Liao, Ying-Chih, Feng-Yu Yen, Fan Hung, Chun-Hao Su, and Wen-Hua Chen. "Intermittent pressurized operation of steam explosion pretreatment system." Journal of the Taiwan Institute of Chemical Engineers 67 (October 2016): 285–91. http://dx.doi.org/10.1016/j.jtice.2016.07.031.

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4

Sue-A-Quan, T. A., A. P. Watkinson, R. P. Gaikwad, C. J. Lim, and B. R. Ferris. "Steam gasification in a pressurized spouted bed reactor." Fuel Processing Technology 27, no. 1 (1991): 67–81. http://dx.doi.org/10.1016/0378-3820(91)90009-2.

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5

Dagbro, Ola, Petteri Torniainen, Olov Karlsson, and Tom Morén. "Colour responses from wood, thermally modified in superheated steam and pressurized steam atmospheres." Wood Material Science and Engineering 5, no. 3-4 (2010): 211–19. http://dx.doi.org/10.1080/17480272.2010.520739.

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6

Beahm, Edward C., Steven R. Daish, William E. Shockley, and Joram Hopenfeld. "Iodine Partitioning in Pressurized Water Reactor Steam Generator Accidents." Nuclear Technology 90, no. 1 (1990): 16–22. http://dx.doi.org/10.13182/nt90-a34382.

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7

Li, M., M. P. Wolcott, F. A. Kamke, and D. A. Dillard. "SMALL SPECIMEN COMPRESSION TESTING IN A PRESSURIZED STEAM ENVIRONMENT." Experimental Techniques 14, no. 3 (1990): 17–19. http://dx.doi.org/10.1111/j.1747-1567.1990.tb01094.x.

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8

Sadeghinia, M., K. M. B. Jansen, L. J. Ernst, and H. Pape. "Mechanical characterization of epoxy moulding compound in pressurized steam." International Journal of Adhesion and Adhesives 40 (January 2013): 103–7. http://dx.doi.org/10.1016/j.ijadhadh.2012.08.006.

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9

Sadeghinia, M., K. M. B. Jansen, L. J. Ernst, et al. "Fracture toughness of Cu–EMC interfaces in pressurized steam." International Journal of Adhesion and Adhesives 49 (March 2014): 73–79. http://dx.doi.org/10.1016/j.ijadhadh.2013.12.002.

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10

CHO, SUNG-KEUN, CHANG-SUNG SEOK, BONG-KOOK BAE, and JAE-MEAN KOO. "EVALUATION OF THE HOOP TENSILE PROPERTIES OF A STEAM GENERATOR TUBE." International Journal of Modern Physics B 20, no. 25n27 (2006): 4129–34. http://dx.doi.org/10.1142/s0217979206040970.

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The steam generators in a pressurized water reactor (PWR) are large heat exchangers that use the heat from the primary reactor coolant to make steam on the secondary-side to drive turbine generators. Hoop stress is known to be the main cause of fracture of inner pressurized tubes such as the steam generator tube. However, because the steam generator tube is too small to be manufactured to a standard tensile specimen in the hoop direction, the axial tensile properties of the steam generator tube (or original material properties) instead of hoop tensile properties have been used to estimate the

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11

Li, Yuen, Chen, et al. "Computational Study of Wet Steam Flow to Optimize Steam Ejector Efficiency for Potential Fire Suppression Application." Applied Sciences 9, no. 7 (2019): 1486. http://dx.doi.org/10.3390/app9071486.

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The steam ejector is a core component of an ejector-based refrigeration system. Additionally, steam ejectors can also be potentially applied for a fire suppression system by using pressurized steam droplets to rapidly quench and extinguish the fire. The use of steam will significantly reduce the amount of water consumption and pipe flow rate compared to conventional sprinklers. However, the efficiency of the steam ejector nozzle is one of major factors that can influence the extinguishing mechanisms and the performance of pressurized steam for fire suppression. In this article, to formulate an

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12

Takamatsu, H., T. Matsunaga, Robert M. Wilson, and T. Kusakabe. "Sludge collector performance in steam generators of pressurized water reactor." Nuclear Engineering and Design 200, no. 1-2 (2000): 295–302. http://dx.doi.org/10.1016/s0029-5493(99)00323-4.

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13

Parsi, A., WA Byers, and J. Deshon. "Surface Analysis of Pressurized Water Reactor Steam Generator Tubing Specimens." Microscopy and Microanalysis 16, S2 (2010): 1636–37. http://dx.doi.org/10.1017/s1431927610054322.

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14

Feliachi, Ali, and Lotfi A. Belblidia. "Optimal Level Controller for Steam Generators in Pressurized Water Reactors." IEEE Power Engineering Review PER-7, no. 6 (1987): 30–31. http://dx.doi.org/10.1109/mper.1987.5527113.

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15

Feliachi, A., and L. A. Belblidia. "Suboptimal level controller for steam generators in pressurized water reactors." IEEE Transactions on Energy Conversion 3, no. 2 (1988): 278–84. http://dx.doi.org/10.1109/60.4731.

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16

Feliachi, Ali, and Lotfi A. Belblidia. "Optimal Level Controller for Steam Generators in Pressurized Water Reactors." IEEE Transactions on Energy Conversion EC-2, no. 2 (1987): 161–67. http://dx.doi.org/10.1109/tec.1987.4765824.

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17

Setiawan, Ikhsan, Makoto Nohtomi, and Masafumi Katsuta. "C07 Design of Thermoacoustic Prime Mover Driven by Pressurized Steam." Proceedings of the Symposium on Stirlling Cycle 2011.14 (2011): 111–14. http://dx.doi.org/10.1299/jsmessc.2011.14.111.

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18

Ragucci, R., P. Giudicianni, and A. Cavaliere. "Cellulose slow pyrolysis products in a pressurized steam flow reactor." Fuel 107 (May 2013): 122–30. http://dx.doi.org/10.1016/j.fuel.2013.01.057.

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19

Roach, William H. "Detection of steam generator tube leaks in pressurized water reactors." Nuclear Engineering and Design 89, no. 1 (1985): 81–89. http://dx.doi.org/10.1016/0029-5493(85)90144-x.

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20

Miccio, Francesco, Elettra Papa, Annalisa Natali Murri, Elena Landi, and Matteo Minelli. "Pressurized Steam Conversion of Biomass Residues for Liquid Hydrocarbons Generation." Energies 14, no. 4 (2021): 1034. http://dx.doi.org/10.3390/en14041034.

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Biomass residues are often considered as a resource if conveniently converted in fuel and alternative feedstock for chemical processes, and their conversion into valuable products may occur by different pathways. This work is focused on the thermochemical conversion at moderate temperature and in steam atmosphere, a mild process in comparison to hydrothermal liquefaction, followed by extraction of soluble products in a solvent. Such process has been already applied to various residues and here extended to the case of marc, the residual pomace from wine making, largely produced worldwide. A pre

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21

Chung, Young-Jong, Soo-Hyong Yang, and Kyoo-Hwan Bae. "A steam or gas pressurizer effect on the system pressure characteristics for an integral pressurized water reactor." Annals of Nuclear Energy 115 (May 2018): 249–55. http://dx.doi.org/10.1016/j.anucene.2018.01.036.

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22

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

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

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23

Yee, Raymond K., and Mike Kapper. "A Structural Integrity Assessment Methodology for Pressurized Vessels." Journal of Pressure Vessel Technology 128, no. 4 (2005): 541–46. http://dx.doi.org/10.1115/1.2349564.

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Pressurized vessels such as a steam drum in a typical power plant can often experience in-service cracking. Structural integrity assessment methodology can be a useful tool to determine the suitability of a vessel for service. This methodology may include fitness-for-service and remaining useful life analyses of a vessel based on the nondestructive examination (NDE) results and operating conditions. In this paper, the structural integrity assessment methodology applied to a steam drum case study is described. The analysis procedure, material property determination, stress analysis, limiting fl

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24

Wang, Yi, Xiao-Wei Guo, Dong Liu, et al. "A 3D Numerical Study of Supersonic Steam Dumping Process of the Pressurizer Relief Tank." Energies 12, no. 12 (2019): 2276. http://dx.doi.org/10.3390/en12122276.

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Simulating the steam dumping process of a pressurized relief tank is a challenging engineering problem, due to the massive computing resource requirements and its complex physical models. This study gave a comprehensive 3D numerical study for the transient dumping process from the PRT (Pressurizer Relief Tank) to the room containing the tank. The physical model, geometry design and meshing strategy, along with the numerical techniques, have been described in detail. Through parallel simulations based on the open source CFD toolbox OpenFOAM, numerical results for the temperature, pressure, and

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25

Tsai, Chiung Wen, Zhi Hao Ren, Jia Lei Ruan, Ting Wang, and Jing Gang Li. "Analysis of Main Steam Line Break for a Pressurized Water Reactor." Applied Mechanics and Materials 764-765 (May 2015): 181–85. http://dx.doi.org/10.4028/www.scientific.net/amm.764-765.181.

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The thermal hydraulics (T-H) code, GINKGO, has been developed by China Nuclear Power Technology Research Institute (CNPTRI) for the transient analyses of pressurized water reactors. GINKGO is designed to simulate the non-loss-of-coolant-accidents (non-LOCAs), and the transients caused by the breaks in secondary side. This paper presents the GINKGO models as well as the analysis of double-ended MSLB that identifies the reactor core characteristics under reactivity feedback. The analysis results show that the variations of reactivity and nuclear power are governed by the competition between posi

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26

Kudo, Shinji, Jun Okada, Shiho Ikeda, Takuya Yoshida, Shusaku Asano, and Jun-ichiro Hayashi. "Improvement of Pelletability of Woody Biomass by Torrefaction under Pressurized Steam." Energy & Fuels 33, no. 11 (2019): 11253–62. http://dx.doi.org/10.1021/acs.energyfuels.9b02939.

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27

Han, Guangping, Wanli Cheng, James Deng, Chunping Dai, Shuyin Zhang, and Qinglin Wu. "Effect of pressurized steam treatment on selected properties of wheat straws." Industrial Crops and Products 30, no. 1 (2009): 48–53. http://dx.doi.org/10.1016/j.indcrop.2009.01.004.

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28

TONE, SETSUJI, SHOICHI KIMURA, YOICHI HINO, and TSUTAO OTAKE. "Potassium catalyzed steam gasification of coal char in a pressurized stream of H2O-H2-CO mixture gas." Journal of Chemical Engineering of Japan 18, no. 2 (1985): 131–36. http://dx.doi.org/10.1252/jcej.18.131.

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29

Li, Guangyu, Luping Wang, Chaowei Wang, Chang’an Wang, Ping Wu, and Defu Che. "Experimental Study on Coal Gasification in a Full-Scale Two-Stage Entrained-Flow Gasifier." Energies 13, no. 18 (2020): 4937. http://dx.doi.org/10.3390/en13184937.

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In this paper, coal gasification characteristics in the reductor were investigated in a full-scale two-stage pressurized entrained-flow gasifier, which has been seldom conducted previously. The present study aimed at elucidating the effects of gasifying agent concentration, coal input rate, and operation period under full reductor load on the performance of a utility two-stage pressurized entrained-flow gasifier for the first time. When the steam input in the combustor was raised from 3318 kg/h to 5722 kg/h, the total outputs of H2, CO, and CO2 were increased by 1765 Nm3/h and 2063 Nm3/h, resp

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30

Hur, D. H., M. S. Choi, D. H. Lee, M. H. Song, and J. H. Han. "Pitting Corrosion and its Countermeasures for Pressurized Water Reactor Steam Generator Tubes." Corrosion 62, no. 10 (2006): 905–10. http://dx.doi.org/10.5006/1.3279900.

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Abstract Pitting corrosion was the primary cause of the Alloy 600 (UNS N06600) steam generator tube degradation in a Korean pressurized water reactor (PWR) plant. Pulled tube examinations and remedial measures were carried out to mitigate the pitting. Based on the destructive examinations, the main causes of pitting corrosion were considered to be the following: accumulated sludge with a high copper content due to corrosion of copper alloys in the secondary system, acidic crevice conditions caused by chloride from condenser leakage, and ingress of air during layup. Countermeasures such as copp

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31

Yang, Guangze, Véronique Pointeau, Etienne Tevissen, and Alexandre Chagnes. "A review on clogging of recirculating steam generators in Pressurized-Water Reactors." Progress in Nuclear Energy 97 (May 2017): 182–96. http://dx.doi.org/10.1016/j.pnucene.2017.01.010.

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32

Jeon, Soon-Hyeok, Seokmin Hong, Hyuk-Chul Kwon, and Do Haeng Hur. "Characteristics of steam generator tube deposits in an operating pressurized water reactor." Journal of Nuclear Materials 507 (August 2018): 371–80. http://dx.doi.org/10.1016/j.jnucmat.2018.05.001.

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33

Kuan, Cheng Chung, Chaung Lin, and Chang Chia Hsu. "Fuzzy Logic Control of Steam Generator Water Level in Pressurized Water Reactors." Nuclear Technology 100, no. 1 (1992): 125–34. http://dx.doi.org/10.13182/nt92-a34758.

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34

Wu, Wencheng, and Chaung Lin. "Optimal Reliable Control System Design for Steam Generators in Pressurized Water Reactors." Nuclear Technology 106, no. 2 (1994): 216–24. http://dx.doi.org/10.13182/nt94-a34977.

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35

Hoehne, Olaf, Stefan Lechner, Matthias Schreiber, and Hans Joachim Krautz. "Drying of Lignite in a Pressurized Steam Fluidized Bed—Theory and Experiments." Drying Technology 28, no. 1 (2009): 5–19. http://dx.doi.org/10.1080/07373930903423491.

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36

Mandal, Sumit, Yehu Lu, Faming Wang, and Guowen Song. "Characterization of Thermal Protective Clothing under Hot Water and Pressurized Steam Exposure." AATCC Journal of Research 1, no. 5 (2014): 7–16. http://dx.doi.org/10.14504/ajr.1.5.2.

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37

Zhou, Chunguang, Christer Rosén, and Klas Engvall. "Biomass oxygen/steam gasification in a pressurized bubbling fluidized bed: Agglomeration behavior." Applied Energy 172 (June 2016): 230–50. http://dx.doi.org/10.1016/j.apenergy.2016.03.106.

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38

L. de Souza-Santos, Marcio, and Juan Villanueva Chavez. "Second Round of Studies on Advanced Power Generation Based on Combined Cycle Using a Single High-Pressure Fluidized Bed Boiler and Consuming Biomass." Open Chemical Engineering Journal 6, no. 1 (2012): 41–47. http://dx.doi.org/10.2174/1874123101206010041.

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Following a preliminary study of power generation processes consuming sugar-cane bagasse; this second round indicates the possibility of almost doubling the current efficiency presently obtained in conventional mills. A combined cycle uses highly pressurized fluidized bed boiler to provide steam above critical temperature to drive steam-turbine cycle while the flue-gas is injected into gas turbines. The present round also shows that gains over usual BIG/GT (Biomass In-tegrated Gasification/Gas Turbine) are very likely mainly due to the practicality of feeding the biomass as slurry that can be

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39

Perovic, V., A. Perovic, G. C. Weatherly, and A. M. Brennenstuhl. "Microstructure and Microchemistry of Inconel 600 STEAM Generator Tubing." Microscopy and Microanalysis 6, S2 (2000): 356–57. http://dx.doi.org/10.1017/s1431927600034279.

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Inconel 600 is an austenitic Ni-Cr-Fe alloy which is extensively used for tubing in steam generators of pressurized light water reactors (PWR) and CANDU heavy water reactors, because of its excellent mechanical properties and corrosion resistance. However, there have been instances of intergranular stress corrosion cracking of tubes in operating steam generators. The chemistry and the structure of grain boundaries and grain boundary precipitation have emerged as factors of prime importance in understanding stress corrosion cracking and intergranular attack of nickel-base alloys (see e.g. ref.

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40

Reddy, G. R., H. S. Kushwaha, S. C. Mahajan, and K. Suzuki. "Decoupling Criteria for Multi-Connected Equipment." Journal of Pressure Vessel Technology 120, no. 1 (1998): 93–98. http://dx.doi.org/10.1115/1.2841892.

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Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water

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41

Hwang, I. S., and I. G. Park. "Control of Alkaline Stress Corrosion Cracking in Pressurized-Water Reactor Steam Generator Tubing." CORROSION 55, no. 6 (1999): 616–25. http://dx.doi.org/10.5006/1.3280503.

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42

Inuil, Masahiro, Yutaka Watanabe, Tatsuo Kondo, Koshi Suzuki, and Kimio Kano. "Crack growth behavior of ferritic steel for USC boilers in pressurized superheated steam." Materials at High Temperatures 18, no. 2 (2001): 119–24. http://dx.doi.org/10.3184/096034001783640603.

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43

Brachi, P., F. Miccio, G. Ruoppolo, and M. Miccio. "Pressurized Steam Torrefaction of Biomass: Focus on Solid, Liquid, and Gas Phase Distributions." Industrial & Engineering Chemistry Research 56, no. 42 (2017): 12163–73. http://dx.doi.org/10.1021/acs.iecr.7b02845.

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44

Leskovar, Matjaž, and Mitja Uršič. "Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor." Nuclear Engineering and Technology 48, no. 1 (2016): 72–86. http://dx.doi.org/10.1016/j.net.2015.08.012.

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45

Hayazi, Nur Farhana, Shaiful Rizam Shamsudin, Rajaselan Wardan, Mohd Syazwan Muhamad Sanusi, and Farah Farhana Zainal. "Graphitization damage on seamless steel tube of pressurized closed-loop of steam boiler." IOP Conference Series: Materials Science and Engineering 701 (December 19, 2019): 012042. http://dx.doi.org/10.1088/1757-899x/701/1/012042.

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46

De, S., and P. K. Nag. "Thermodynamic analysis of a partial gasification pressurized combustion and supercritical steam combined cycle." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 214, no. 6 (2000): 565–74. http://dx.doi.org/10.1243/0957650001538100.

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47

GRANET, IRVING. "SOME CONSIDERATIONS IN THE DESIGN OF STEAM GENERATORS FOR PRESSURIZED WATER REACTOR SYSTEMS." Journal of the American Society for Naval Engineers 70, no. 3 (2009): 471–79. http://dx.doi.org/10.1111/j.1559-3584.1958.tb01752.x.

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48

WATANABE, Yutaka, Hiroto TAMURA, Tatuo KONDOU, and Akimitchi HISINUMA. "314 Oxidation properties of Ti-Al-V intermetallic compound in pressurized superheated steam." Proceedings of Conference of Tohoku Branch 2000.35 (2000): 106–7. http://dx.doi.org/10.1299/jsmeth.2000.35.106.

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49

Inuil, Masahiro, Yutaka Watanabe, Tatsuo Kondo, Koshi Suzuki, and Kimio Kano. "Crack growth behavior of ferritic steel for USC boilers in pressurized superheated steam." Materials at High Temperatures 18, no. 2 (2001): 119–24. http://dx.doi.org/10.1179/mht.2001.013.

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50

Ahmad, Murni M., Chai K. Chiew, Abrar Inayat, and Suzana Yusup. "Simulation of Integrated Pressurized Steam Gasification of Biomass for Hydrogen Production using iCON." Journal of Applied Sciences 11, no. 21 (2011): 3593–99. http://dx.doi.org/10.3923/jas.2011.3593.3599.

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