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On The Structure Property Correlation And The Evolution Of Nanofeatures In 12 135 Cr Oxide Dispersion Strengthened Ferritic Steels
Download On The Structure Property Correlation And The Evolution Of Nanofeatures In 12 135 Cr Oxide Dispersion Strengthened Ferritic Steels full books in PDF, epub, and Kindle. Read online On The Structure Property Correlation And The Evolution Of Nanofeatures In 12 135 Cr Oxide Dispersion Strengthened Ferritic Steels ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis On the structure-property correlation and the evolution of Nanofeatures in 12-13.5% Cr oxide dispersion strengthened ferritic steels by : He, Pei
Download or read book On the structure-property correlation and the evolution of Nanofeatures in 12-13.5% Cr oxide dispersion strengthened ferritic steels written by He, Pei and published by KIT Scientific Publishing. This book was released on 2013-12-24 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt: Main objective of this work is to develop, by systematic variation of the chemical composition, and TMP, 14% Cr nano-structured ferritic alloys with significantly improved high-temperature properties compared to currently available ODS alloys. Application of state-of-the-art characterization tools shall lead to an integrated understanding of structure-property correlation and the formation mechanism of nanoparticles.
Book Synopsis Teaching Fractions and Ratios for Understanding by : Susan J. Lamon
Download or read book Teaching Fractions and Ratios for Understanding written by Susan J. Lamon and published by Routledge. This book was released on 2020-03-23 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written in a user-friendly, conversational style, the fourth edition of this groundbreaking text helps pre-service and in-service mathematics teachers build the comfort and confidence they need to begin talking to children about fractions and ratios, distilling complex ideas and translating research into usable ideas for the classroom. For two decades, Teaching Fractions and Ratios for Understanding has pushed readers beyond the limits of their current understanding of fractions and rational numbers, challenging them to refine and explain their thinking without falling back on rules and procedures they have relied on throughout their lives. All of the material offered in the book has been used with students, and is presented so that readers can see the brilliance of their insights as well as the issues that challenge their understanding. Each chapter includes children’s strategies and samples of student work for teacher analysis, as well as activities for practicing each thinking strategy, designed to be solved without rules or algorithms, using reasoning alone. The fourth edition of this popular text has been updated throughout and includes new examples of student work, updated artwork, and more. As with previous editions, an equally valuable component of this text is the companion book MORE! Teaching Fractions and Ratios for Understanding (2012), a supplement that is not merely an answer key but a resource that provides the scaffolding for the groundbreaking approach to fraction and ratio instruction explored here. MORE! includes in-depth discussions of selected problems in the main text, supplementary activities, Praxis preparation questions, more student work, and templates for key manipulatives.
Book Synopsis Characterization and Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation by :
Download or read book Characterization and Modeling of Grain Boundary Chemistry Evolution in Ferritic Steels Under Irradiation written by and published by . This book was released on 2016 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic/martensitic (FM) steels such as HT-9, T-91 and NF12 with chromium concentrations in the range of 9-12 at.% Cr and high Cr ferritic steels (oxide dispersion strengthened steels with 12-18% Cr) are receiving increasing attention for advanced nuclear applications, e.g. cladding and duct materials for sodium fast reactors, pressure vessels in Generation IV reactors and first wall structures in fusion reactors, thanks to their advantages over austenitic alloys. Predicting the behavior of these alloys under radiation is an essential step towards the use of these alloys. Several radiation-induced phenomena need to be taken into account, including phase separation, solute clustering, and radiation-induced segregation or depletion (RIS) to point defect sinks. RIS at grain boundaries has raised significant interest because of its role in irradiation assisted stress corrosion cracking (IASCC) and corrosion of structural materials. Numerous observations of RIS have been reported on austenitic stainless steels where it is generally found that Cr depletes at grain boundaries, consistently with Cr atoms being oversized in the fcc Fe matrix. While FM and ferritic steels are also subject to RIS at grain boundaries, unlike austenitic steels, the behavior of Cr is less clear with significant scatter and no clear dependency on irradiation condition or alloy type. In addition to the lack of conclusive experimental evidence regarding RIS in F-M alloys, there have been relatively few efforts at modeling RIS behavior in these alloys. The need for predictability of materials behavior and mitigation routes for IASCC requires elucidating the origin of the variable Cr behavior. A systematic detailed high-resolution structural and chemical characterization approach was applied to ion-implanted and neutron-irradiated model Fe-Cr alloys containing from 3 to 18 at.% Cr. Atom probe tomography analyses of the microstructures revealed slight Cr clustering and segregation to dislocations and grain boundaries in the ion-irradiated alloys. More significant segregation was observed in the neutron irradiated alloys. For the more concentrated alloys, irradiation did not affect existing Cr segregation to grain boundaries and segregation to dislocation loops was not observed perhaps due to a change in the dislocation loop structure with increasing Cr concentration. Precipitation of [alpha]' was observed in the neutron irradiated alloys containing over 9 at.% Cr. However ion irradiation appears to suppress the precipitation process. Initial low dose ion irradiation experiments strongly suggest a cascade recoil effect. The systematic analysis of grain boundary orientation on Cr segregation was significantly challenged by carbon contamination during ion irradiation or by existing carbon and therefore carbide formation at grain boundaries (sensitization). The combination of the proposed systematic experimental approach with atomistic modeling of diffusion processes directly addresses the programmatic need for developing and benchmarking predictive models for material degradation taking into account atomistic kinetics parameters.
Book Synopsis Development of Oxide Dispersion Strengthened Ferritic Steels for Fusion by :
Download or read book Development of Oxide Dispersion Strengthened Ferritic Steels for Fusion written by and published by . This book was released on 1998 with total page 189 pages. Available in PDF, EPUB and Kindle. Book excerpt: An oxide dispersion strengthened (ODS) ferritic steel with high temperature strength has been developed in line with low activation criteria for application in fusion power systems. The composition Fe-13.5Cr-2W-0.5Ti-0.25Y2O3 was chosen to provide a minimum chromium content to insure fully delta-ferrite stability. High temperature strength has been demonstrated by measuring creep response of the ODS alloy in uniaxial tension at 650 and 900 C in an inert atmosphere chamber. Results of tests at 900 C demonstrate that this alloy has creep properties similar to other alloys of similar design and can be considered for use in high temperature fusion power system designs. The alloy selection process, materials production, microstructural evaluation and creep testing are described.
Book Synopsis Development Oxide Dispersion Strengthened Ferritic Steels for Fusion by :
Download or read book Development Oxide Dispersion Strengthened Ferritic Steels for Fusion written by and published by . This book was released on 1997 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Uniaxial tension creep response is reported for an oxide dispersion strengthened (ODS) steel, Fe-13.5Cr-2W-0.5Ti-0.25 Y2O3 (in weight percent) manufactured using the mechanical alloying process. Acceptable creep response is obtained at 900°C.
Book Synopsis Atomic Scale Characterisation of Oxide Dispersion Strengthened Steels for Fusion Applications by : Ceri Williams
Download or read book Atomic Scale Characterisation of Oxide Dispersion Strengthened Steels for Fusion Applications written by Ceri Williams and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced-activation ferritic steels are considered as the primary candidate materials for structural applications within nuclear fusion power plants. It is known that by mechanically alloying ferritic steel powder with Y (usually in the form ofY203) then consolidating the material by hot isostatic pressing, a nanoscale dispersion of oxygen rich nanoclusters as small as ~2nm is introduced into the microstructure. This vastly improves high temperature strength and creep resistance, and the nanoclusters also act as trapping sites for helium and point defects produced under irradiation. In this thesis, the evolution of the oxide nanoclusters in a Fe-14Cr-2W-0.3Ti & 0.3Y203 ODS alloy was investigated primarily using atom probe tomography. The microstructure was characterized at various points during processing to give an insight into the factors influencing the formation of the nanoclusters. It was found that the nanoclusters nucleated during the mechanical alloying stage, then followed near classical nucleation and growth mechanisms keeping the same composition of ~8%Y, ~12%Ti,~2S%O and ~4S%Cr throughout. The formation and evolution of S-lSnm grain boundary oxides was also observed, and these were shown to form first as Cr203 particles that subsequently transform into a Y-Ti-O based oxide on further processing. The influence of mechanical alloying with 0.Swt.%Fe2Y rather than 0.3wt.%Y203 was also investigated, and this showed that there was no difference in the final microstructure produced provided the level of Ti in the starting powder was tightly controlled. Without sufficient Ti, the nanoclusters were Y-O based and ~6nm diameter. Both the Y-O and Y-Ti-O nanoclusters were moderately stable on annealing at 1200°C for up to 100 hours, with only minimal coarsening observed. Ti was found not to influence the coarsening rate of the nanoclusters significantly. The stability of the oxide nanoclusters under irradiation was investigated by using Fe2+ ion irradiation to simulate displacement cascade damage in the ODS-Eurofer material (the official European candidate material for testing in the ITER fusion test reactor). Doses up to ~6 dpa at 400°C were used, and there was no significant change to the nanocluster distribution. However segregation of Mn to dislocations was observed after irradiation. These results indicate that ODS steels are good candidate structural materials, as the microstructure is stable at high temperature and under irradiation. The starting powders, and processing parameters need to be tightly controlled in order to produce the optimal material for use in service.
Book Synopsis Development of Low Activation Oxide Dispersion Strengthened Ferritic Steels for Fusion Reactors by : Debkumar Mukhopadhyay
Download or read book Development of Low Activation Oxide Dispersion Strengthened Ferritic Steels for Fusion Reactors written by Debkumar Mukhopadhyay and published by . This book was released on 1996 with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evolution of Microstructure during Long‐term Creep of a Tempered Martensite Ferritic Steel by : Ali Aghajani Bazazi
Download or read book Evolution of Microstructure during Long‐term Creep of a Tempered Martensite Ferritic Steel written by Ali Aghajani Bazazi and published by Cuvillier Verlag. This book was released on 2009-12-08 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: Tempered martensite ferritic steels are used for critical components in fossil fired power plants that operate in the creep range. The materials contain a high density of dislocations and precipitates form on all types of internal interfaces, the majority of which represent subgrain boundaries. Most previous studies suffer from either only relating to short term creep experiments or from being incomplete in not considering all relevant elements of the microstructure. No systematic effort was made to investigate the evolution of microstructures under conditions of long term creep. In the present study the evolution of the microstructure of a 12% Cr tempered martensite ferritic steel was investigated under conditions of long term aging and creep. Transmission electron microscopy (TEM) and electron back scattered diffraction (EBSD) techniques were used to characterize materials from interrupted creep tests (0.5%, 1%, 1.6% and rupture at 11.9%; creep conditions: 550°C, 120 MPa, rupture time: 139 971 h). It is shown that subgrains coarsen, that the close correlation between carbides and subgrain boundaries loosens during long term creep, and that the frequency of small angle boundaries increases. In addition, the evolution of dislocation densities during long term aging and creep was studied using high angle annular dark field (HAADF) scanning transmission electron microscopy (STEM). During aging the dislocation density remains constant, while during long term creep the dislocation density continuously decreases. All these elementary deformation processes have already been discussed in short term creep studies. The present study shows that they also govern long term creep, however, during long term creep, precipitation and coarsening reactions occur which are not observed during short term creep. Cr rich M23C6, VX carbides and Laves phase were identified as the major precipitates in the microstructure of the 12% Chromium tempered martensite ferritic steel. Their chemical compositions, sizes, volume fractions and number densities were evaluated in all interrupted specimens. M23C6 particles coarsen and establish their equilibrium concentration after 51072 hours. VX particles are stable. The Laves phase particles do not reach thermodynamic equilibrium as they form and grow during long term creep. This is due to Silicon which is found in the Laves phase particles and which diffuses slowly in the steel matrix.
Book Synopsis The Effect of High Temperature Exposure on the Structure and Properties of Ferritic Oxide Dispersion Strengthened Alloys by : Mehmet Turker
Download or read book The Effect of High Temperature Exposure on the Structure and Properties of Ferritic Oxide Dispersion Strengthened Alloys written by Mehmet Turker and published by . This book was released on 1993 with total page 266 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix by : P. Dubuisson
Download or read book Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phenix written by P. Dubuisson and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper deals with the irradiation behavior of the oxide dispersion strengthened (ODS) ferritic alloy DT2203Y05, a 13% Cr ferritic alloy strengthened by a fine dispersion of yttrium and titanium oxides. This alloy was irradiated up to 81 dpa in Phénix as fuel pin cladding. The profilometry measurements confirm its high swelling resistance. Few voids, mainly associated with oxides, are observed at low irradiation temperatures, but this alloy is severely embrittled by irradiation. A few cracks are observed in the lower 2/3 of the fissile column, and the longitudinal tensile tests show hardening and severe ductility loss induced by irradiation along the whole fuel column.
Book Synopsis Innovative Powder Processing of Oxide Dispersion Strengthened ODS Ferritic Stainless Steels by :
Download or read book Innovative Powder Processing of Oxide Dispersion Strengthened ODS Ferritic Stainless Steels written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An innovative gas atomization reaction synthesis technique was employed as a viable method to dramatically lower the processing cost for precursor oxide dispersion forming ferritic stainless steel powders (i.e., Fe-Cr-(Hf, Ti)-Y). During this rapid solidification process the atomized powders were enveloped by a nano-metric Cr-enriched metastable oxide film. Elevated temperature heat treatment was used to dissociate this metastable oxide phase through oxygen exchange reactions with Y-(Hf, Ti) enriched intermetallic compound precipitates. These solid state reactions resulted in the formation of highly stable nano-metric mixed oxide dispersoids (i.e., Y-Ti-O or Y-Hf-O) throughout the alloy microstructure. Subsequent high temperature (1200 C) heat treatments were used to elucidate the thermal stability of each nano-metric oxide dispersoid phase. Transmission electron microscopy coupled with X-ray diffraction was used to evaluate phase evolution within the alloy microstructure.
Book Synopsis Dispersion-strengthened Ferritic Steels as Fast Reactor Structural Materials by : J. Huet
Download or read book Dispersion-strengthened Ferritic Steels as Fast Reactor Structural Materials written by J. Huet and published by . This book was released on 1973 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nanostructures in a Ferritic and an Oxide Dispersion Strengthened Steel Induced by Dynamic Plastic Deformation by : Zhenbo Zhang
Download or read book Nanostructures in a Ferritic and an Oxide Dispersion Strengthened Steel Induced by Dynamic Plastic Deformation written by Zhenbo Zhang and published by . This book was released on 2015 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Optimization and Testing Results of Zr-bearing Ferritic Steels by :
Download or read book Optimization and Testing Results of Zr-bearing Ferritic Steels written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. Ferritic-martensitic (FM) steels are important structural materials for nuclear reactors due to their advantages over other applicable materials like austenitic stainless steels, notably their resistance to void swelling, low thermal expansion coefficients, and higher thermal conductivity. However, traditional FM steels exhibit a noticeable yield strength reduction at elevated temperatures above ~500°C, which limits their applications in advanced nuclear reactors which target operating temperatures at 650°C or higher. Although oxide-dispersion-strengthened (ODS) ferritic steels have shown excellent high-temperature performance, their extremely high cost, limited size and fabricability of products, as well as the great difficulty with welding and joining, have limited or precluded their commercial applications. Zirconium has shown many benefits to Fe-base alloys such as grain refinement, improved phase stability, and reduced radiation-induced segregation. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of a new generation of Zr-bearing ferritic alloys to be fabricated using conventional steelmaking practices, which have excellent radiation resistance and enhanced high-temperature creep performance greater than Grade 91.
Book Synopsis Structural Alloys for Nuclear Energy Applications by : Robert Odette
Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Book Synopsis Nanomaterials by Severe Plastic Deformation by : Michael J. Zehetbauer
Download or read book Nanomaterials by Severe Plastic Deformation written by Michael J. Zehetbauer and published by John Wiley & Sons. This book was released on 2006-03-06 with total page 872 pages. Available in PDF, EPUB and Kindle. Book excerpt: These proceedings of the "Second International Conference on Nanomaterials by Severe Plastic Deformation" review the enormous scientific avalanche that has been developing in the field over recent years. A valuable resource for any scientist and engineer working in this emerging field of nanotechnology.
Book Synopsis Phase-field Modeling of Phase Changes and Mechanical Stresses in Electrode Particles of Secondary Batteries by : Zhang, Tao
Download or read book Phase-field Modeling of Phase Changes and Mechanical Stresses in Electrode Particles of Secondary Batteries written by Zhang, Tao and published by KIT Scientific Publishing. This book was released on 2021-09-27 with total page 224 pages. Available in PDF, EPUB and Kindle. Book excerpt: Most storage materials exhibit phase changes, which cause stresses and, thus, lead to damage of the electrode particles. In this work, a phase-field model for the cathode material NaxFePO4 of Na-ion batteries is studied to understand phase changes and stress evolution. Furthermore, we study the particle size and SOC dependent miscibility gap of the nanoscale insertion materials. Finally, we introduce the nonlocal species concentration theory, and show how the nonlocality influences the results.
