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Corrosion Of Candidate Materials In Molten Flibe Salt For Application In Fluoride Salt Cooled Reactors
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Book Synopsis Corrosion of Candidate Materials in Molten FLiBe Salt for Application in Fluoride-salt Cooled Reactors by : Thomas Jonathan Chrobak
Download or read book Corrosion of Candidate Materials in Molten FLiBe Salt for Application in Fluoride-salt Cooled Reactors written by Thomas Jonathan Chrobak and published by . This book was released on 2018 with total page 215 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Corrosion Behavior of Alloys in Molten Fluoride Salts by :
Download or read book Corrosion Behavior of Alloys in Molten Fluoride Salts written by and published by . This book was released on 2015 with total page 336 pages. Available in PDF, EPUB and Kindle. Book excerpt: The molten fluoride salt-cooled high-temperature nuclear reactor (FHR) has been proposed as a candidate Generation IV nuclear reactor. This reactor combines the latest nuclear technology with the use of molten fluoride salt as coolant to significantly enhance safety and efficiency. However, an important challenge in FHR development is the corrosion of structural materials in high-temperature molten fluoride salt. The structural alloys' degradation, particularly in terms of chromium depletion, and the molten salt chemistry are key factors that impact the lifetime of nuclear reactors and the development of future FHR designs. In support of materials development for the FHR, the nickel base alloy of Hastelloy N and iron-chromium base alloy 316 stainless steel are being actively considered as critical structural alloys. Enriched 27LiF-BeF2 (named as FLiBe) is a promising coolant for the FHR because of its neutronic properties and heat transfer characteristics while operating at atmospheric pressure. In this study, the corrosion behavior of Ni-5Cr and Ni-20Cr binary model alloys, and Hastelloy N and 316 stainless steel in molten FLiBe with and without graphite were investigated through various microstructural analyses. Based on the understanding of the corrosion behavior and data of above four alloys in molten FLiBe, a long-term corrosion prediction model has been developed that is applicable specifically for these four materials in FLiBe at 700°C. The model uses Cr concentration profile C(x, t) as a function of corrosion distance in the materials and duration fundamentally derived from the Fick's diffusion laws. This model was validated with reasonable accuracy for the four alloys by fitting the calculated profiles with experimental data and can be applied to evaluate corrosion attack depth over the long-term. The critical constant of the overall diffusion coefficient (Deff) in this model can be quickly calculated from the experimental measurement of alloys' weight loss due to Cr depletion. While many factors affect the Deff such as the grain boundary type, grain size, precipitates, initial Cr concentration as well as temperature, this model provides a methodology for estimating corrosion attack depth of alloys in molten fluoride salts obviating the need for difficult and challenging experiment.
Book Synopsis Corrosion and Electrochemistry Studies for Molten Salt Reactor Alloy Development by : William H. Doniger
Download or read book Corrosion and Electrochemistry Studies for Molten Salt Reactor Alloy Development written by William H. Doniger and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Molten Salt Reactor (MSR) concept is attracting considerable interest as the next generation nuclear reactor because it provides key benefits, including, (i) high degree of passive safety, (ii) atmospheric pressure operation, (iii) high thermal efficiency, (iv) fuel design flexibility and (v) lower spent fuel per unit energy. Fluoride salt-cooled reactors are being actively developed for deployment because of the desirable thermophysical properties of fluoride salts, such as low melting and high boiling points, and high specific heat capacities and thermal conductivities, as well as their low cross sections for thermal neutron absorption. However, molten fluoride salts can be quite corrosive to structural materials at the intended high operating temperatures of MSRs due to the inherent instability of protective oxide layers induced by the inevitable presence of even trace levels of impurities in the salt. Of particular concern is the corrosion of the alloying element Cr which is present in notable concentrations in most high temperature alloys primarily for air-side oxidation resistance. For the successful implementation of MSRs, there is need for: (a) a greater understanding of the corrosion mechanisms in structural alloys, (b) development of electrochemical methods to evaluate materials based on electrochemical parameters that govern the thermodynamics and kinetics of corrosion, and (c) development of electrochemical methods to test and monitor the evolving chemistry of the molten salt to assess and control corrosion. In this research, a holistic approach to studying molten salt corrosion is undertaken through both static corrosion and electrochemistry experiments to address these scientific and engineering challenges. Two types of fluoride salts have been used for this research: (i) LiF-BeF2 (66-34 mol %) (FLiBe), which is being considered either as the coolant in conjunction with solid TRISO fuel particles or as solvent salt for dissolving the fuel, and (ii) LiF-NaF-KF (46.5-11.5-42 mol %) (FLiNaK), which is a candidate for secondary coolant loop systems and also serves as a surrogate for understanding the mechanisms of corrosion in a wide range of fluoride salts. Molten fluoride salt experiments are inherently challenging due to the hygroscopicity and toxicity of the fluoride salts, the high temperatures of these experiments, and the extreme sensitivity of materials to corrosive impurities in the molten salt. The study involved significant engineering for designing and constructing experimental systems for safely preparing and handling fluoride salts both with and without beryllium. These systems offered a versatile environment to conduct corrosion and electrochemistry experiments accurately and reproducibly.
Book Synopsis CORROSION BEHAVIOR OF REACTOR MATERIALS IN FLUORIDE SALT MIXTURES. by :
Download or read book CORROSION BEHAVIOR OF REACTOR MATERIALS IN FLUORIDE SALT MIXTURES. written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program culminated in the selection of a high-strength Nibase alloy containing 17% Mo, 7% Cr, and 5% Fe. The results of several long-term corrosion loops and in-pile capsule tests completed with this alloy are reviewed to demonstrate the excellent corrosion resistance of this alloy composition to fluoride salt mixtures at high temperatures. Methods based on thermodynamic properties of the alloy container and fused salt are presented for predicting corrosion rates in these systems. The results of radiotracer studies conducted to demonstrate the proposed corrosion model also are discussed. (auth).
Book Synopsis Molten Salts Chemistry by : FREDERIC Lantelme
Download or read book Molten Salts Chemistry written by FREDERIC Lantelme and published by Elsevier. This book was released on 2013-08-30 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten salts and fused media provide the key properties and the theory of molten salts, as well as aspects of fused salts chemistry, helping you generate new ideas and applications for fused salts. Molten Salts Chemistry: From Lab to Applications examines how the electrical and thermal properties of molten salts, and generally low vapour pressure are well adapted to high temperature chemistry, enabling fast reaction rates. It also explains how their ability to dissolve many inorganic compounds such as oxides, nitrides, carbides and other salts make molten salts ideal as solvents in electrometallurgy, metal coating, treatment of by-products and energy conversion. This book also reviews newer applications of molten salts including materials for energy storage such as carbon nano-particles for efficient super capacitors, high capacity molten salt batteries and for heat transport and storage in solar plants. In addition, owing to their high thermal stability, they are considered as ideal candidates for the development of safer nuclear reactors and for the treatment of nuclear waste, especially to separate actinides from lanthanides by electrorefining.
Book Synopsis Corrosion in Molten Fluoride Salt by : Cody Falconer
Download or read book Corrosion in Molten Fluoride Salt written by Cody Falconer and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: As the concentration of greenhouse gases in the environment continues to reach levels that have never been recorded in history, the demand for low greenhouse gas emitting forms of energy is reaching an all-time high. With current public opinion and geopolitical changes occurring, Generation IV nuclear energy systems are ready to help transition energy production away from the consumption of fossil fuels. While not necessarily a new idea, the Generation IV Molten Salt Reactor (MSR) design has garnered a significant amount of interest from both government agencies and private companies alike, making it a critical reactor design for research.Originally developed in the mid-twentieth century, the MSR was successfully demonstrated by Oak Ridge National Laboratory, but little interest has been expressed in MSR designs until recently. In order for the development and deployment of MSRs to be successful today, there is a need for understanding how code-certified alloys, as well as new materials, are going to perform in a molten salt environment. A prototypical approach in literature at investigating the performance of materials in molten salt environments has become the use of static isothermal salt exposure testing cells. Unfortunately, there exists no standard method for these tests which has resulted in a large scattering of material data coming out of research efforts. Literature has suggested that this scattering is a direct result of variations in the design of the static isothermal salt exposure test cell. In this dissertation, several aspects that go into the design of static isothermal salt exposure test cells are studied to see how variations in the test cell can affect the material's behavior in these tests. The size of the test cell effectively creates a limit on a test parameter referred to as the volume of salt to exposed surface area ratio (Vol/SA). In this work, it is shown that adjusting this ratio results in dramatically different rates of corrosion in 316H stainless steel (316HSST) samples exposed to a LiF-NaF-KF salt mixture known as FLiNaK. At small ratios, the corrosion rate of 316HSST actually appears to plateau after only 500 hrs of salt exposure whereas a higher ratio continues corroding 316HSST beyond 1000 hrs. This result shows an obvious challenge then for determining the true behavior of 316HSST in FLiNaK salt. It is then speculated that a new way of ranking material's performance in salt qualitatively could be by determining the corrosion plateau time for a given material in a given Vol/SA ratio at a given temperature. Intimately tied to the Vol/SA ratio is the effect that the purity of the FLiNaK salt has on the material performance. Molten salts are highly sensitive to the levels of impurities in them and changes to the impurity levels can dramatically change how aggressive the salts are towards materials in them. In this dissertation, 316HSST was exposed to purified and as-received FLiNaK salt and it can clearly be observed that the purification process for the FLiNaK salt improved the corrosion rate of the 316HSST as a result of impurity removal. The final area of investigation in this dissertation was the effects that dissimilar materials have on one another when coexisting in the same FLiNaK salt. Traditional interaction mechanisms between dissimilar materials like galvanic coupling were shown to have little if no effect on the interaction of dissimilar metals submerged in FLiNaK. The main driving force for interaction of dissimilar materials in FLiNaK was demonstrated to be through a mechanism referred to as activity gradient driven mass transportation which is primarily enabled through the disproportionation reaction of corrosion products. Activity gradient driven mass transportation is accurately predicted through computational tools and is shown to dramatically alter how 304SST samples behave in FLiNaK. Additionally, this mechanism is expected to have a large effect on materials interactions with graphite in MSR designs, and a novel design for eliminating this interaction is investigated.
Book Synopsis Molten Salts Chemistry by : Frederic Lantelme
Download or read book Molten Salts Chemistry written by Frederic Lantelme and published by Newnes. This book was released on 2013-08-14 with total page 592 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten salts and fused media provide the key properties and the theory of molten salts, as well as aspects of fused salts chemistry, helping you generate new ideas and applications for fused salts.Molten Salts Chemistry: From Lab to Applications examines how the electrical and thermal properties of molten salts, and generally low vapour pressure are well adapted to high temperature chemistry, enabling fast reaction rates. It also explains how their ability to dissolve many inorganic compounds such as oxides, nitrides, carbides and other salts make molten salts ideal as solvents in electrometallurgy, metal coating, treatment of by-products and energy conversion.This book also reviews newer applications of molten salts including materials for energy storage such as carbon nano-particles for efficient super capacitors, high capacity molten salt batteries and for heat transport and storage in solar plants. In addition, owing to their high thermal stability, they are considered as ideal candidates for the development of safer nuclear reactors and for the treatment of nuclear waste, especially to separate actinides from lanthanides by electrorefining. Explains the theory and properties of molten salts to help scientists understand these unique liquids Provides an ideal introduction to this expanding field Illustrated text with key real-life applications of molten salts in synthesis, energy, nuclear, and metal extraction
Book Synopsis Purification and Chemical Control of Molten Li2BeF4 for a Fluoride Salt Cooled Reactor by :
Download or read book Purification and Chemical Control of Molten Li2BeF4 for a Fluoride Salt Cooled Reactor written by and published by . This book was released on 2015 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Out of the many proposed generation IV, high-temperature reactors, the molten salt reactor (MSR) is one of the most promising. The first large scale MSR, the molten salt reactor experiment (MSRE), operated from 1965 to 1969 using Li2BeF4, or flibe, as a coolant and solvent for uranium fluoride fuel, at maximum temperatures of 654°C, for over 15000 hours. The MSRE experienced no concept breaking surprises and was considered a success. Newly proposed designs of molten salt reactors use solid fuels, making them less exotic compared to the MSRE. However, any molten salt reactor will require a great deal of research pertaining to the chemical and mechanical mastery of molten salts in order to prepare it for commercialization. To supplement the development of new molten salt reactors, approximately 100 kg of flibe was purified using the standard hydrofluorination process. Roughly half of the purified salt was lithium-7 enriched salt from the secondary loop of the MSRE. Purification rids the salt of impurities and reduces its capacity for corrosion, also known as the redox potential. The redox potential of flibe was measured at various stages of purification for the first time using a dynamic beryllium reference electrode. These redox measurements have been superimposed with metal impurities measurements found by neutron activation analysis. Lastly, reductions of flibe with beryllium metal have been investigated. Over reductions have been performed, which have shown to decrease redox potential while seemingly creating a beryllium-beryllium halide system. Recommendations of the lowest advisable redox potential for corrosion tests are included along with suggestions for future work.
Book Synopsis Corrosion of Ferritic Steels in High Temperature Molten Salt Coolants for Nuclear Applications by :
Download or read book Corrosion of Ferritic Steels in High Temperature Molten Salt Coolants for Nuclear Applications written by and published by . This book was released on 2008 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion of ferritic steels in high temperature molten fluoride salts may limit the life of advanced reactors, including some hybrid systems that are now under consideration. In some cases, the steel may be protected through galvanic coupling with other less noble materials with special neutronic properties such a beryllium. This paper reports the development of a model for predicting corrosion rates for various ferritic steels, with and without oxide dispersion strengthening, in FLiBe (Li2BeF4) and FLiNaK (Li-Na-K-F) coolants at temperatures up to 800 C. Mixed potential theory is used to account for the protection of steel by beryllium, Tafel kinetics are used to predict rates of dissolution as a function of temperature and potential, and the thinning of the mass-transfer boundary layer with increasing Reynolds number is accounted for with dimensionless correlations. The model also accounts for the deceleration of corrosion as the coolants become saturated with dissolved chromium and iron. This paper also reports electrochemical impedance spectroscopy of steels at their corrosion potentials in high-temperature molten salt environments, with the complex impedance spectra interpreted in terms of the interfacial charge transfer resistance and capacitance, as well as the electrolyte conductivity. Such in situ measurement techniques provide valuable insight into the degradation of materials under realistic conditions.
Book Synopsis Molten Salt Reactors and Thorium Energy by : Thomas James Dolan
Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts Covers MSR applications, technical issues, reactor types and reactor designs Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Book Synopsis Influence of Environmental Conditions and Proton Irradiation on Molten Salt Corrosion of Metals by : Weiyue Zhou (Scientist in nuclear science and engineering)
Download or read book Influence of Environmental Conditions and Proton Irradiation on Molten Salt Corrosion of Metals written by Weiyue Zhou (Scientist in nuclear science and engineering) and published by . This book was released on 2021 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis contributes to our understanding of corrosion of metals in high temperature molten salts, especially fuorides.
Book Synopsis Enhanced Molten Salt Purification by Electrochemical Methods by :
Download or read book Enhanced Molten Salt Purification by Electrochemical Methods written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten salts are considered within the Very High Temperature Reactor program as heat transfer media because of their intrinsically favorable thermo-physical properties at temperatures starting from 300 C and extending up to 1200 C. In this context two main applications of molten salt are considered, both involving fluoride-based materials: as primary coolants for a heterogeneous fuel reactor core and as secondary heat transport medium to a helium power cycle for electricity generation or other processing plants, such as hydrogen production. The reference design concept here considered is the Advanced High Temperature Reactor (AHTR), which is a large passively safe reactor that uses solid graphite-matrix coated-particle fuel (similar to that used in gas-cooled reactors) and a molten salt primary and secondary coolant with peak temperatures between 700 and 1000 C, depending upon the application. However, the considerations included in this report apply to any high temperature system employing fluoride salts as heat transfer fluid, including intermediate heat exchangers for gas-cooled reactor concepts and homogenous molten salt concepts, and extending also to fast reactors, accelerator-driven systems and fusion energy systems. The most important initial requirement for heat transfer test of molten salt systems is the establishment of reference coolant materials to use in the experiments. An earlier report produced within the same project (INL/EXT-10-18297) highlighted how thermo-physical properties of the materials that directly impact the heat transfer behavior are strongly correlated to the of composition and impurities concentration of the melt. It is therefore essential to establish laboratory techniques that can measure the melt composition, and to develop purification methods that would allow the production of large quantities of coolant with the desired purity. A companion report titled 'An experimental test plan for the characterization of molten salt thermo-chemistry properties in heat transport systems' describes the options available to reach such objectives and contains extended references to published work. The report highlights how electrochemical methods are the most promising techniques for the development of instrumentation aimed at the measurement of melts composition and for enhanced purification systems. The purpose of this work is to summarize preliminary experimental activities performed at the INL Safety and Tritium Applied Research facility in support of the development of electrochemistry based instrumentation and purification systems. The experiments have been focused on the LiF-BeF2 eutectic (67 and 33 mol%, respectively), also known as flibe.
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis TMS 2017 146th Annual Meeting & Exhibition Supplemental Proceedings by : The Minerals, Metals & Materials Society TMS
Download or read book TMS 2017 146th Annual Meeting & Exhibition Supplemental Proceedings written by The Minerals, Metals & Materials Society TMS and published by Springer. This book was released on 2017-02-18 with total page 777 pages. Available in PDF, EPUB and Kindle. Book excerpt: This collection features papers presented at the 146th Annual Meeting & Exhibition of The Minerals, Metals & Materials Society.
Book Synopsis Molten Salts Chemistry and Technology by : Marcelle Gaune-Escard
Download or read book Molten Salts Chemistry and Technology written by Marcelle Gaune-Escard and published by John Wiley & Sons. This book was released on 2014-05-12 with total page 902 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written to record and report on recent research progresses in the field of molten salts, Molten Salts Chemistry and Technology focuses on molten salts and ionic liquids for sustainable supply and application of materials. Including coverage of molten salt reactors, electrodeposition, aluminium electrolysis, electrochemistry, and electrowinning, the text provides researchers and postgraduate students with applications include energy conversion (solar cells and fuel cells), heat storage, green solvents, metallurgy, nuclear industry, pharmaceutics and biotechnology.
Book Synopsis Nuclear Corrosion Science and Engineering by : Damien Feron
Download or read book Nuclear Corrosion Science and Engineering written by Damien Feron and published by Elsevier. This book was released on 2012-02-21 with total page 1073 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
Author :National Aeronautics and Space Adm Nasa Publisher :Independently Published ISBN 13 :9781730797057 Total Pages :70 pages Book Rating :4.7/5 (97 download)
Book Synopsis Molten Salt Corrosion of Sic and Si3n4 by : National Aeronautics and Space Adm Nasa
Download or read book Molten Salt Corrosion of Sic and Si3n4 written by National Aeronautics and Space Adm Nasa and published by Independently Published. This book was released on 2018-11-03 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: Industrial systems such as heat engines and heat exchangers involve harsh environments. The structural materials are subjected to high temperatures as well as corrosive gases and condensed phases. Past experience with metal alloys has shown that these condensed phases can be particularly corrosive and are often the limiting factor in the operation of these systems. In a heat engine the most common condensed corrodent is Na2SO4 whereas in a heat exchanger an oxide slag may be present. The primary emphasis is on Na2SO4 induced corrosion, however, similarities and differences to oxide slag are also discussed. The extensive research on corrosion of metal alloys has led to understanding and controlling corrosion for these materials. Currently silicon based ceramics are prime candidates for the applications discussed. Therefore it is important to understand the effects of condensed phase deposits on this emerging class of high temperature materials. Both the thermodynamic and strength of the ceramic is also examined. Finally some control strategies for corrosion of silicon based ceramics are explored. Jacobson, Nathan S. and Smialek, James L. and Fox, Dennis S. Glenn Research Center...
