Relevant bibliographies by topics / Lead-bismuth alloys Corrosion

Academic literature on the topic 'Lead-bismuth alloys Corrosion'

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Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Lead-bismuth alloys Corrosion"

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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.

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Deloffre, 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.

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Konys, 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.

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Abstract Liquid metals have been used in various applications in nuclear systems. Lead-bismuth eutectic (LBE) is foreseen as a coolant and target for neutron generation in accelerator-driven systems (ADS), whereas pure lead will be used as coolant in Gen IV-type lead-cooled fast reactors (LFR). The advantage of heavy liquid metal alloys is their high thermal conductivity and their relative safety in case of an accident. A major problem in non-isothermal systems is the corrosion of their structural components, consisting mainly of ferritic/martensitic and austenitic stainless steels, since the solubility of dissolved elements depends strongly on temperature. The formation of oxide scales on structural components is considered a viable approach to limiting the corrosion rates. To maintain a specific oxygen content in lead or LBE, an oxygen control system (OCS) is crucial. This requires continuous measurement of the oxygen activity in the liquid metal by means of electrochemical sensors. It must be assured that no oxides of the liquid metal itself are formed; otherwise, the system can be blocked. Therefore, this paper addresses the development of oxygen sensors for corrosion control of martensitic and austenitic steels in a lead-bismuth eutectic system at Forschungszentrum Karlsruhe (FZK, Eggenstein-Leopoldshafen, Germany).
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Lee, 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.

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The corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10−6 wt.%. The obtained corrosion surfaces of post-processed samples were characterized by several microscopy methods. Up to 1000 h, all the alloys exhibited an evolution of duplex oxide layers, which were spalled until 2000 h due to their increased thickness and decreased integrity. Following the spallation, a thin internal Cr-rich oxide layer was formed above the Cr-depleted zone for T91 and HT9. SS316L was penetrated by LBE down to 300 μm in severe cases. A comparison on the corrosion depths of the materials with regard to the parabolic oxidation law with abundant literature data suggests that it may lose its validity once the duplex layer is destroyed as it allows LBE to penetrate the metal substrate.
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Samui, 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.

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Lead–Bismuth Eutectic (LBE) is a heavy metal liquid alloy used as a coolant for compact high temperature reactors (CHTRs), fast breeder reactor (FBRs) and as a spallation target for ADS. In spite of many advantages due to its thermophysical properties, corrosion towards structural materials remains one of the major issues of LBE. In absence of any oxygen impurity, corrosion in LBE is driven by dissolution processes and the solubility of the main elements of the structural material alloys. Using the CALPHAD method, Thermo-Calc software, a thermodynamic database was developed to assess the interaction between Ni and LBE coolant. The solubilities of Ni in LBE, Bi and Pb liquids have been calculated at different temperatures.
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Lim, 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.

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Li, 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.

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Lam, 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.

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9

Short, 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.

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Ryabov, 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.

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Both in the domestic and world steel industry alternative ecologically clean free-cutting steels, having cutting machinability characteristics and mechanicalproperties, comparable with lead-containing steels, but voided of their drawbacks,are actively searched. First ofall the alternative steels should not be not so ecologically harmful. Scientific and technological aspects of lead-free free-machining steels production, alloyed by bismuth, calcium, tin, boron and nitrogen presented. Solubility of bismuth in iron and iron alloys with chromium, manganese, nickel, tungsten, vanadium, cobalt,phosphor, sulphur, aluminum, carbon and other elements at the temperature of 1550–1650 ºСdetermined. Parameters of interaction of the first and second order calculated. Study of bismuth behavior and tin spherical samples in 40X steel melt accomplished. The study done at the high temperature facility with controlled atmosphere and X-ray TV observation system. Simulation of phase compositions multicomponent alloys of steel АВЦ40ХГНМaccomplished by application of a program package FactSage. Within the study,a production technology of lead-free, ecologically clean free-machining, steels elaborated and masteredat OJSC “Zlatoust electro-metallurgical works”. Free-machining corrosion-resistant steels (АВЦ19ХГН, АВЦ40Х, АВЦ40ХГНМ, АВЦ12Х18Н10, АВЦ40Х13, АВЦ14Х17Н2) alloyed by bismuth and calcium, steels (АО40Х, АО30ХМ) alloyed by tin, and steels (А38ХГМАРand А30ХМАР) containing BN were the objects of the study. The steels samples were in the form of forged billet of 10, 20 and 80 mm diameter and ingots of 18 and 500 kg (round 345 mm). Steel quality characteristics determined such as mechanicalproperties in longitudinal and cross directions of ingots, uniformity of distribution of fusible elements, carbon and Sulphur along the axis zone and in billet transverse sections. Pictures of ingots macrostructure by height and section obtained. Estimation of hardenability and steel contamination by non-metallic inclusions, austenitic grain size, steel machinability by cutting, surfacequality of re-worked billet and steel macrostructure accomplished. Comparable ecological studies of atmosphere contamination during the steel alloying also accomplished.
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Dissertations / Theses on the topic "Lead-bismuth alloys Corrosion"

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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.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 2008.
Includes 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.
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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.

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Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.
Includes 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.
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Conference papers on the topic "Lead-bismuth alloys Corrosion"

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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.

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Abstract For the mass production of astatine-211, a promising radiopharmaceutical for cancer treatment, the National Institute for Quantum and Radiological Science and Technology has proposed the innovative “Liquid Bismuth Target System.” The target window in this system must be made from a material that resists the highly corrosive liquid bismuth environment. To meet this requirement, a promising target window material was selected in corrosion experiments performed in stagnant liquid bismuth. Based on knowledge of corrosion in liquid lead–bismuth eutectic gained during the development of fast reactors and accelerator-driven subcritical systems, FeCrMo–alloy, FeCrAl–alloy, and austenitic stainless steel (as a reference) were selected as the specimen materials. Experiments were carried out under saturated dissolved oxygen and low oxygen conditions, and the corrosion behaviors of the specimens were evaluated, mainly by scanning electron microscopy. The FeCrAl–alloy exhibited the most excellent corrosion resistance, followed by FeCrMo–alloy. Both materials are suitable candidates for the target window. Although austenitic stainless steel was less corrosion resistant than the former two materials, it is a likely applicable for the target window under appropriately limited operation conditions (such as irradiation current and exposure time) of the liquid bismuth target system.
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Balbaud-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.

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Among the Generation IV systems, Sodium Fast Reactors (SFR) are promising and benefit of considerable technological experience. However, the availability and the acceptability of the SFR are affected by the problems linked with the sodium-water reaction. One innovative solution to this problem is the replacement of the sodium in the secondary loops by an alternative liquid fluid. Among the fluids considered, lead-bismuth is at the moment being evaluated, liquid lead-bismuth has been considerably studied in the frame of the research program on Accelerator Driven Systems for transmutation applications. However, lead alloys are corrosive towards structural materials. The main parameters impacting the corrosion rate of Fe-Cr martensitic steels (considered as structural materials) are the nature of the steel (material side), the temperature, the liquid alloy velocity and the dissolved oxygen concentration (liquid alloy side). In this study, attention is focused on the behaviour of Fe-9Cr steels and more particularly T91 martensitic steel. It has been shown that in the case of Fe-Cr martensitic steels the corrosion process depends on the concentration of oxygen dissolved in Pb-Bi. - For an oxygen concentration lower than the one necessary for magnetite formation (approximately < 10−8 wt% at T ≈ 500 °C for Fe-9Cr steels), corrosion proceeds by dissolution of the steel. - For a higher oxygen content dissolved in Pb-Bi, corrosion proceeds by oxidation of the steel. These two corrosion processes have been experimentally and theoretically studied in CEA Saclay and also by other partners leading to some corrosion modelling in order to predict the life duration of these materials as well as their limits of utilisation. This study takes into account the two kinds of corrosion processes, dissolution and oxidation. In these two different processes, the lead alloy physico-chemical parameters are considered: the temperature and the liquid alloy velocity for both processes and the oxygen concentration for oxidation.
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Kurata, 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.

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Small and medium reactors using lead alloys as coolant are one of the promising reactor concepts with improved safety because of their thermal-physical and chemical properties. This paper focuses on development of Al-alloy coating for nuclear systems using liquid lead-bismuth eutectic (LBE). Since corrosion attack becomes severe against structural steels at high temperatures in liquid LBE, it is necessary to improve corrosion resistance of steels. An Al-alloy coating method using Al, Ti and Fe powders, and laser beam heating has been developed. Main defects formed in an Al-powder-alloy coating process are surface defects and cracks. Conditions required to avoid these defects are employment of the laser beam scanning rate of 20 mm/min and adjustment of the Al concentration in the coating layer. According to results of the corrosion tests at 550°C in liquid LBE, the Al-alloy coating layers on 316SS protect severe corrosion attack such as grain boundary corrosion and LBE penetration observed in 316SS without coating. The good corrosion resistance of the Al-alloy coating is based on the thin Al-oxide film which can be regenerated in liquid LBE. From the viewpoints of the soundness of produced Al-powder-alloy coating layers and preservation of their corrosion resistance, it is estimated that the range of the adequate Al concentration in the coating layer is from 4 to 12 wt%.
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Schroer, 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.

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The concept of minimizing steel corrosion in liquid lead-alloys by addition of oxygen strongly depends on the availability of efficient devices for oxygen transfer and reliable oxygen sensors. The accuracy of electrochemical oxygen sensors is analyzed on the basis of theoretical considerations and results from experiments in stagnant lead-bismuth eutectic (LBE). Additionally, the feasibility of gas/liquid oxygen-transfer and the long-term performance of electrochemical sensors in flowing liquid metal are addressed based on operation of the CORRIDA loop, a facility for testing steels in flowing LBE.
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Zhang, 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.

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The competition between corrosion and oxidation on a steel surface immersed in lead alloys with controlled oxygen leads to different oxide-layer characteristics as compared with those formed in gases. The presence of a liquid metal [liquid lead or lead-bismuth eutectic (LBE)] can either enhance or reduce the oxidation rate, resulting in different oxide growth rates and microstructures. Based on analysis of experimental results in static LBE/lead and gases under the same experimental conditions, we predict the oxide-layer structure and thickness as functions of immersion time and analyze the factors that play important roles in the oxidation process in LBE/lead. It is shown that there is a significant difference between the oxide formed in liquid lead alloys and in gases, including the oxide-layer structure. To generate a stable protective oxide layer on steel surfaces in LBE, the long-term corrosion effect, the supply of oxygen, and the penetration of the liquid metal into the structural materials or oxide layers must be taken into account.
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Marti´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.

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Lead bismuth eutectic (LBE) has been proposed as a candidate for coolant and/or as spallation target material of an Accelerator Driven Systems (ADS) and as coolant for a Generation IV reactor, the Lead-cooled Fast Reactor (LFR). Lead and lead alloys, such as lead-bismuth eutectic (LBE), are efficient heat transfer media because of high thermal conductivity and high heat capacity. However, one of the critical issues in the design of these systems is the compatibility of steels with LBE. Therefore, it is important to know the behaviour of steels under conditions similar to which can be expected during the course of reactor operation. Corrosion tests using a liquid metal loop provide result very useful. Forced convection loop in CIEMAT, LINCE, was designed for long-term corrosion tests in LBE. It consists in a centrifugal pump, an exchange heater, a refrigerator, a storage tank, two tests areas (hot and cold) and tubing to connect the previous components. The volume of LBE is 300 litres and the flow rate approximately 1m/s. The maximum temperature is 450°C and the minimum 300°C, which means a temperature gradient of 150°C, and it is controlled by 25 temperature regulators. The electrical power is 80kW. An oxygen control system (OCS) has been implemented in the loop. The corrosion behaviour of AISI 316L and T91 steels is being investigated in flowing lead-bismuth eutectic (LBE) at 300 and 450 °C for 2000 and 5000 h. The tests are performed in the LINCE loop, under controlled oxygen activity in LBE. The results obtained show that neither material exhibited a weight loss after exposure to the flowing LBE at 300°C instead 5000 h. However, probes exposure at 450°C show important weight loss after 5000 h.
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Di 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.

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Oxygen has a fundamental role for the safe operation of GEN IV reactors cooled by Heavy Liquid Metals, HLM. The use of oxygen sensors and dosing the gas in the environment are key issues for the chemistry control of HLMs, in particular when corrosion of structural materials is of concern. In fact, the oxygen concentration must be high enough to grow a protective oxide scale on the surface of the construction materials (steels) in order to prevent their dissolution in the liquid metal. On the other hand, a certain threshold must not be exceeded to prevent precipitation of oxides within the flow paths of the plant. For measuring and controlling the concentration of dissolved oxygen in liquid lead alloys, electrochemical sensors were developed and have been studied for several years. This study focuses on the work carried out in the CVR, in the convection loop COLONRI I, containing liquid Lead-Bismuth Eutectic, LBE. This vertical loop has several locations where sensors can be placed for monitoring of the local oxygen content. A research study was initiated on the aim of assessing the response and reliability of the sensors in various locations, when different gases were dosed in the liquid metal. For over 1000 hours the sensors were monitored as variables, such as oxygen content and temperature, were changed. Their response as a function of their position was qualitatively evaluated and discussed.
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Song, 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.

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KAERI (Korea Atomic Energy Research Institute) is developing an accelerator-driven transmutation system called HYPER (HYbrid Power Extraction Reactor). HYPER is the 1000MWth system designed to transmute the long-lived TRU (Transuranic Elements) and FP (Fission Product) included in the PWR spent fuel. LBE (Lead-Bismuth Eutectic) is used as the spallation target and coolant material in HYPER. KAERI has also investigated the conceptual design of a lead-cooled fast reactor. Lead (Pb) is used as the coolant material in that reactor. The most significant problem is a corrosion when using the lead-alloy liquid metal in those reactors. Therefore, it is necessary to study the corrosion characteristics and develop the technology to protect the steel structure materials against a corrosion. KAERI has been developing the facilities needed to study the corrosion of lead-alloy. KAERI fabricated a static corrosion test facility in 2003. The static corrosion tests of HT-9, 316L and T91 have been performed at 600 °C and 650 °C since 2003. The Pb-Bi loop was constructed in 2006. The Pb-Bi loop is an isothermal loop which can be operated at temperatures up to 550 °C. The Pb loop is designed to be operated with ΔT = 150 °C (Tmin = 450 °C and Tmax = 600 °C). The first stage of the Pb loop construction was finished and operations began in 2006. We will complete the second stage of the Pb loop construction after testing the first stage Pb loop.
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Nakazima, 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.

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A concept of steam lift pump type lead-bismuth cooled fast reactor (SLPLFR) is proposed as high temperature and high efficiency Pb-Bi cooled fast reactors. Fe-Al alloy-surface treated steels and ceramics of SiC, Si3N4 and SiC/SiC composites have been chosen as candidates of cladding and structural materials, respectively. A corrosion test plan is proposed, where compatibility of steels applied with Al-Fe alloy-surface treatment and the ceramics will be tested in high temperature Pb-Bi flow. A conceptual design of a test apparatus for the corrosion test is provided.
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Frazer, 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.

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In order to increase the thermal efficiency and produce process heat for hydrogen production, the operating temperature of the heat-transfer fluid in thermal solar plants needs to increase, but to increase the operating temperature, new heat-transport liquids need to be evaluated. Liquid metals have been proposed as heat-transport fluids because of the large temperature ranges over which they remain liquid. One of the most studied liquid metals for non-solar applications has been lead-bismuth eutectic alloy (LBE), for the nuclear industry. The main challenge with using LBE as a coolant is that the major constituents of structural steels have high solubility in LBE. In this work, the challenges of using LBE as a high temperature heat-transport fluid are discussed, as well as initial results of high-temperature static corrosion tests of structural steels to evaluate their potential use in a thermal solar power plant.
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