Добірка наукової літератури з теми "Lead-bismuth alloys Corrosion"
Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями
Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Lead-bismuth alloys Corrosion".
Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.
Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.
Статті в журналах з теми "Lead-bismuth alloys Corrosion"
Aerts, A., S. Gavrilov, G. Manfredi, A. Marino, K. Rosseel, and J. Lim. "Oxygen–iron interaction in liquid lead–bismuth eutectic alloy." Physical Chemistry Chemical Physics 18, no. 29 (2016): 19526–30. http://dx.doi.org/10.1039/c6cp01561a.
Повний текст джерелаDeloffre, Ph, A. Terlain, and F. Barbier. "Corrosion and deposition of ferrous alloys in molten lead–bismuth." Journal of Nuclear Materials 301, no. 1 (February 2002): 35–39. http://dx.doi.org/10.1016/s0022-3115(01)00724-3.
Повний текст джерелаKonys, J., C. Schroer, and O. Wedemeyer. "Electrochemical Oxygen Sensors for Corrosion Control in Lead-Cooled Nuclear Reactors." Corrosion 65, no. 12 (December 1, 2009): 798–808. http://dx.doi.org/10.5006/1.3319106.
Повний текст джерелаLee, Seung Gi, Yong-Hoon Shin, Jaeyeong Park, and Il Soon Hwang. "High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application." Applied Sciences 11, no. 5 (March 6, 2021): 2349. http://dx.doi.org/10.3390/app11052349.
Повний текст джерелаSamui, Pradeep, and Renu Agarwal. "Thermodynamic Assessment and Solubility of Ni in LBE Coolants." Thermo 2, no. 4 (October 20, 2022): 371–82. http://dx.doi.org/10.3390/thermo2040025.
Повний текст джерелаLim, Jun, Hyo On Nam, Il Soon Hwang, and Ji Hyun Kim. "A study of early corrosion behaviors of FeCrAl alloys in liquid lead–bismuth eutectic environments." Journal of Nuclear Materials 407, no. 3 (December 2010): 205–10. http://dx.doi.org/10.1016/j.jnucmat.2010.10.018.
Повний текст джерелаLi, Bingsheng, Yanbin Sheng, Huiping Liu, Xirui Lu, Xiaoyan Shu, Anli Xiong, and Xu Wang. "Dissolution corrosion of 4H‐SiC in lead‐bismuth eutectic at 550°C." Materials and Corrosion 70, no. 10 (May 24, 2019): 1878–83. http://dx.doi.org/10.1002/maco.201910777.
Повний текст джерелаLam, L. T., T. D. Huynh, N. P. Haigh, J. D. Douglas, D. A. J. Rand, C. S. Lakshmi, P. A. Hollingsworth, J. B. See, J. Manders, and D. M. Rice. "Influence of bismuth on the age-hardening and corrosion behaviour of low-antimony lead alloys in lead/acid battery systems." Journal of Power Sources 53, no. 1 (January 1995): 63–74. http://dx.doi.org/10.1016/0378-7753(94)02159-z.
Повний текст джерелаShort, M. P., R. G. Ballinger, and H. E. Hänninen. "Corrosion resistance of alloys F91 and Fe–12Cr–2Si in lead–bismuth eutectic up to 715°C." Journal of Nuclear Materials 434, no. 1-3 (March 2013): 259–81. http://dx.doi.org/10.1016/j.jnucmat.2012.11.010.
Повний текст джерелаRyabov, A. V. "Mastering of production of lead-free ecologically clean free-machining steels." Ferrous Metallurgy. Bulletin of Scientific , Technical and Economic Information 75, no. 3 (June 27, 2019): 337–43. http://dx.doi.org/10.32339/0135-5910-2019-3-337-343.
Повний текст джерелаДисертації з теми "Lead-bismuth alloys Corrosion"
Wang, Yunzhi (Yunzhi Diana). "Static corrosion of candidate alloys for the lead-bismuth fast reactor." Thesis, Massachusetts Institute of Technology, 2008. http://hdl.handle.net/1721.1/45266.
Повний текст джерелаIncludes bibliographical references (leaves 41-42).
This project examined the corrosion rates and mechanisms of two candidate alloys for use in Lead-bismuth Eutectic (LBE) cooled fast nuclear reactors. The two alloys examined were T91 and Fe-12Cr-2Si. An experimental study was performed to analyze the static corrosion on the two alloys. For the experiment, the polished samples of the two alloys were heated in LBE for 166 hours at 700 The heating conditions, such as temperature, oxygen levels, and moisture levels were monitored closely throughout the duration of the experiment. During the heating process, hydrogen gas was bubbled into the LBE, creating a highly reducing environment. Argon was used as a cover gas. Upon removal from the furnace, the alloy samples were examined via optical microscopy, scanning electron microscopy, and X-ray diffraction analysis. Examination of the samples found no observable corrosion effects on the Fe-12Cr-2Si samples and a thin layer of magnetite on the T91 sample.
by Yunzhi (Diana) Wang.
S.B.
Lim, Jeongyoun. "Effects of chromium and silicon on corrosion of iron alloys in lead-bismuth eutectic." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41288.
Повний текст джерелаIncludes bibliographical references.
The high power densities and temperatures expected for next generation nuclear applications, including power generation and transmutation systems, will require new types of heat transport systems to be economic. Present interest in heavy liquid metal coolants, especially in lead and lead-bismuth eutectic, originates from such requirements as increased heat removal capacity and enhanced safety features. However, corrosion of structural metals represents a major limiting factor in developing advanced liquid Pb-alloy coolant technology. In fact, the development of advanced structural and cladding alloys that are resistant to corrosion over a wide range of oxygen potentials in this environment would represent the enabling technology for these systems. The goal of this research was to develop a class of Fe-Cr Si alloys that are resistant to corrosion in Pb and Pb alloys at temperatures of 6000C or higher. As a necessary part of this development effort, an additional goal was to further develop the fundamental understandings of the mechanisms by which corrosion protection is achieved. A series of alloys based on the Fe-Cr-Si system were proposed as potential candidates for this application. These alloys were then produced and evaluated. The results of this evaluation verified the hypothesis that an Fe alloys with suitable levels of Cr (>12 wt%) and Si (> 2.5 wt%) will be protected by either a tenacious oxide film (over a wide range of oxygen potentials above the formation potential for Cr and Si oxides) or by a low solubility surface region (at low oxygen potentials) Experimental results obtained from model alloys after lead-bismuth eutectic exposure at 6000C demonstrated the film formation process.
(cont.) The hypothesis that Si addition would promote the formation of a diffusion barrier was confirmed by the actual reduction of oxide thickness over time. The Si effect was magnified by the addition of Cr to the system. Based on a kinetic data assessment on the experimental results of Fe-Si and Fe-Cr-Si alloys, the synergetic alloying effect of Cr and Si was revealed. An improved understanding on the kinetic process and its dependence on the alloying elements has been achieved.
by Jeongyoun Lim.
Sc.D.
Тези доповідей конференцій з теми "Lead-bismuth alloys Corrosion"
Takai, Toshihide, Tomohiro Furukawa, Shigeki Watanabe, and Noriko S. Ishioka. "Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-63277.
Повний текст джерелаBalbaud-Ce´le´rier, F., and L. Martinelli. "Modelling of Fe-Cr Martensitic Steels Corrosion in Liquid Lead Alloys." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75292.
Повний текст джерелаKurata, Yuji, Hitoshi Yokota, and Tetsuya Suzuki. "Development of Aluminum Alloy Coating for Advanced Nuclear Systems Using Lead Alloys." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6545.
Повний текст джерелаSchroer, Carsten, Olaf Wedemeyer, and Juergen Konys. "Aspects of Minimizing Steel Corrosion in Liquid Lead-Alloys by Addition of Oxygen." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29726.
Повний текст джерелаZhang, Jinsuo, and Ning Li. "Comparisons of the Oxide Layer Between Static Liquid-Bismuth-Eutectic and Gas Environments." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89066.
Повний текст джерелаMarti´n-Mun˜oz, F. J., L. Soler-Crespo, and D. Go´mez-Bricen˜o. "Corrosion Behaviour of Steels in Lead-Bismuth Eutectic (LBE) in the LINCE Loop Up to 5000 h." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-76011.
Повний текст джерелаDi Gabriele, Fosca, and Lukas Kosek. "Oxygen Monitoring in the Natural Convection Loop Colonri I." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16483.
Повний текст джерелаSong, Tae Yung, Choonho Cho, and Chungho Cho. "The Lead-Alloy Corrosion Study at KAERI." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89600.
Повний текст джерелаNakazima, Toru, Abu Khalid Rivai, Koji Hata, Vaclav Dostal, and Minoru Takahashi. "Study Plan for Material Corrosion Test in Lead and Bismuth Eutectic at High Temperature." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89420.
Повний текст джерелаFrazer, D., C. Cionea, M. Popovic, Y. Aussat, A. J. Gubser, and P. Hosemann. "Lead-Bismuth Eutectic as a High Temperature Heat-Transport Fluid for Thermal Solar Power." In ASME 2014 8th International Conference on Energy Sustainability collocated with the ASME 2014 12th International Conference on Fuel Cell Science, Engineering and Technology. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/es2014-6528.
Повний текст джерела