Download or read book Irradiation Damage in Neutron irradiated Fe Cr Model Alloys written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Tolerance of Neutron Irradiated Model Fe Cr Al Alloys written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Fe Cr Al alloy system has the potential to form an important class of enhanced accident-tolerant cladding materials in the nuclear power industry owing to the alloy system's higher oxidation resistance in high-temperature steam environments compared with traditional zirconium-based alloys. However, radiation tolerance of Fe Cr Al alloys has not been fully established. In this study, a series of Fe Cr Al alloys with 10 18 wt % Cr and 2.9 4.9 wt % Al were neutron irradiated at 382 C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition. Dislocation loops with Burgers vector of a/2 111 and a 100 were detected and quantified. Results indicate precipitation of Cr-rich is primarily dependent on the bulk chromium composition. Mechanical testing of sub-size-irradiated tensile specimens indicates the hardening response seen after irradiation is dependent on the bulk chromium composition. A structure property relationship was developed; it indicated that the change in yield strength after irradiation is caused by the formation of these radiation-induced defects and is dominated by the large number density of Cr-rich precipitates at sufficiently high chromium contents after irradiation.

Download or read book Neutron Irradiation Damage in Ferrltic Fe Cr Alloys written by DS. Gelles and published by . This book was released on 1990 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent work on microstructural development in a series of ferritic alloys following irradiation in the Fast Flux Test Facility (FFTF) is presented. the series includes Fe-Cr binary alloys ranging from 3 to 18 chromium, and substitutional ferritic alloys based on Fe-10Cr with minor additions of silicon, manganese, vanadium, tantalum, and zirconium. Irradiations were performed to fluences as high as 30 dpa at 425°C. the simple Fe-Cr binary alloy behavior following irradiation to 15 dpa was found to be similar to that observed following irradiation in EBR-II. All specimens contained radiation damage such as dislocation loops and voids. Swelling was highest, 0.26%, in the Fe-9Cr alloy with a corresponding dislocation network comprising equal parts of a?100? and a/2 ?111? Burger's vectors. Less swellings was found in other alloys with a corresponding dislocation structure composed mainly of a?100? loops. An example of a deformation slip band containing elongated voids was found, which indicated that channel fracture may occur in ferritic alloys that contain uniform void swelling.

Download or read book Fundamentals of Radiation Materials Science written by GARY S. WAS and published by Springer. This book was released on 2016-07-08 with total page 1014 pages. Available in PDF, EPUB and Kindle. Book excerpt: The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys. Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics. The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking. The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals. Reviews of the first edition: "...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or as a good references compilation for experimented readers." - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008 “The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science.” - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.

Download or read book Thin Film Analysis by X Ray Scattering written by Mario Birkholz and published by John Wiley & Sons. This book was released on 2006-05-12 with total page 378 pages. Available in PDF, EPUB and Kindle. Book excerpt: With contributions by Paul F. Fewster and Christoph Genzel While X-ray diffraction investigation of powders and polycrystalline matter was at the forefront of materials science in the 1960s and 70s, high-tech applications at the beginning of the 21st century are driven by the materials science of thin films. Very much an interdisciplinary field, chemists, biochemists, materials scientists, physicists and engineers all have a common interest in thin films and their manifold uses and applications. Grain size, porosity, density, preferred orientation and other properties are important to know: whether thin films fulfill their intended function depends crucially on their structure and morphology once a chemical composition has been chosen. Although their backgrounds differ greatly, all the involved specialists a profound understanding of how structural properties may be determined in order to perform their respective tasks in search of new and modern materials, coatings and functions. The author undertakes this in-depth introduction to the field of thin film X-ray characterization in a clear and precise manner.

Download or read book Modeling of Radiation induced Segregation in Austenitic Fe Cr Ni Alloys written by Todd Randall Allen and published by . This book was released on 1997 with total page 926 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Postirradiation Deformation Behavior in Ferritic Fe Cr Alloys written by PL. Gardner and published by . This book was released on 1994 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: It has been demonstrated that fast neutron irradiation produces significant hardening in simple Fe-(3-18)Cr binary alloys irradiated to about 35 dpa in the temperature range 365 to 420°C, whereas irradiation at 574°C produces hardening only for 15% or more chromium. The irradiation-induced changes in tensile properties are discussed in terms of changes in the power law work hardening exponent. The work hardening exponent of the lower chromium alloys decreased significantly after low temperature irradiation (

Download or read book Modelling of Radiation Damage in Fe Cr Alloys written by L. Malerba and published by . This book was released on 2007 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Cr ferritic/martensitic steels are being considered as structural materials for a large number of future nuclear applications, from fusion to accelerator-driven systems and GenIV reactors. Fe-Cr alloys can be used as model materials to investigate some of the mechanisms governing their microstructure evolution under irradiation and its correlation to changes in their macroscopic properties. Focusing on these alloys, we show an example of how the integration of computer simulation and theoretical models can provide keys for the interpretation of a host of relevant experimental observations. In particular we show that proper accounting for two basic features of these alloys, namely, the existence of a fairly strong attractive interaction between self-interstitials and Cr atoms and of a mixing enthalpy that changes sign from negative to positive around 8 to 10 % Cr, is a necessary and, to a certain extent, sufficient condition to rationalize and understand their behavior under irradiation. These features have been revealed by ab initio calculations, are supported by experimental evidence, and have been adequately transferred into advanced empirical interatomic potentials, which have been and are being used for the simulation of damage production, defect behavior, and phase transformation in these alloys. The results of the simulations have been and are being used to parameterize models capable of extending the description of radiation effects to scales beyond the reach of molecular dynamics. The present paper intends to highlight the most important achievements and results of this research activity.

Download or read book Neutron Irradiation Rate Dependence of Damage Structures in Fe Cu Model Alloys written by T. Yoshiie and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fe-Cu model alloys and pure iron were irradiated at 573 K under two different neutron flux conditions (9.4 x 10-8 dpa/s and 1.1 x 10-9 dpa/s) up to about 0.008 dpa. Although defect clusters were not detected by TEM in any specimen, the results of positron lifetime measurement and mechanical property tests clearly indicated an irradiation rate dependence on the microvoid formation and mechanical properties. In positron lifetime measurements, the size of microvoids under low flux irradiation was larger than under high flux irradiation. But the number density was lower than high flux irradiation. In mechanical property testing, more hardening occurred by low flux irradiation. The irradiation rate dependence increased with copper content. These results suggest that the dependence is caused by the precipitation of copper. As copper migrates mainly by the vacancy mechanism, the size and the density of precipitates increase with increasing vacancy migration distance, which becomes longer with a decreasing of the irradiation rate.

Download or read book Ductility and Hardening of Neutron Irradiated Fe Cr and Fe Cr Ni Steels written by N. Igata and published by . This book was released on 1992 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fe-Cr and Fe-Ni-Cr steels are candidate alloys for fusion reactor materials. For future design it is important to clarify the general rules of mechanical properties for those alloys irradiated at higher fluence and at higher temperatures. In this investigation, to find general rules for irradiation effects, twelve kinds of commercial Fe-Cr and Fe-Ni-Cr steels were irradiated in JMTR. The total flux was 6 x 1025n/m2, and the irradiation temperature was 743 to 848 K. Yield strength, tensile strength, and uniform ductility at room temperature were observed for all specimens before and after irradiation, and work-hardening exponents were obtained from stress-strain curves of those specimens. In all cases, uniform ductility was equal to the work-hardening exponent, there was a close relationship between strength and uniform ductility, and there was no anomalous behavior in these alloy series. Further study was made of Fe-9Cr-2Mo steel, which was irradiated to 3 x 1026 n/m2 at 673 to 923 K in EBR-II. Electron micrographs for controlled or irradiated specimens were used for the analysis of the change of strength by irradiation. The strength and uniform ductility was interpreted from microstructural aspects.

Download or read book Irradiation Effects on Structural Materials written by Spencer H. Bush and published by . This book was released on 1964 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Postirradiation Deformation Behavior in Ferritic Fe Cr Alloys written by and published by . This book was released on 1992 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: It has been demonstrated that fast-neutron irradiation produces significant hardening in simple Fe-(3-18)Cr binary alloys irradiated to about 35 dpa in the temperature range 365 to 420°C, whereas irradiation at 574°C produces hardening only for 15% or more chromium. The irradiation-induced changes in tensile properties are discussed in terms of changes in the power law work-hardening exponent. The work-hardening exponent of the lower chromium alloys decreased significantly after low-temperature irradiation ((less-than or equal to) 420°C) but increased after irradiation at 574°C. The higher chromium alloys failed either in cleavage or in a mixed ductile/brittle fashion. Deformation microstructures are presented to support the tensile behavior.

Download or read book Transmission Electron Microscopy written by David B. Williams and published by Springer Science & Business Media. This book was released on 2013-03-09 with total page 708 pages. Available in PDF, EPUB and Kindle. Book excerpt: Electron microscopy has revolutionized our understanding the extraordinary intellectual demands required of the mi of materials by completing the processing-structure-prop croscopist in order to do the job properly: crystallography, erties links down to atomistic levels. It now is even possible diffraction, image contrast, inelastic scattering events, and to tailor the microstructure (and meso structure ) of materials spectroscopy. Remember, these used to be fields in them to achieve specific sets of properties; the extraordinary abili selves. Today, one has to understand the fundamentals ties of modem transmission electron microscopy-TEM of all of these areas before one can hope to tackle signifi instruments to provide almost all of the structural, phase, cant problems in materials science. TEM is a technique of and crystallographic data allow us to accomplish this feat. characterizing materials down to the atomic limits. It must Therefore, it is obvious that any curriculum in modem mate be used with care and attention, in many cases involving rials education must include suitable courses in electron mi teams of experts from different venues. The fundamentals croscopy. It is also essential that suitable texts be available are, of course, based in physics, so aspiring materials sci for the preparation of the students and researchers who must entists would be well advised to have prior exposure to, for carry out electron microscopy properly and quantitatively.

Download or read book TEM of Neutron Proton and Self ion Irradiation Damage in FeCr Alloys written by Jack Haley and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Study of Irradiation Damage in Iron and Fe Cr Alloys written by Shuo Xu and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Swelling Suppression in Phosphorus Modified Fe Cr Ni Alloys During Neutron Irradiation written by EH. Lee and published by . This book was released on 1990 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Phosphorus-containing austenitic alloys in the solution annealed condition were irradiated at 745 to 760 K (470 to 485°C) in the Fast Flux Test Facility (FFTF) reactor to doses ranging from 0.1 to 10 dpa. The alloys were variations on Fe-13Cr-15Ni-0.05P with respective additions of 0.8 silicon, 0.2 titanium, or 0.8 silicon plus 0.2 titanium; also included were low (0.01) and zero phosphorus compositions (all values in wt %). This alloy set was studied previously using heavy ion irradiations.

Download or read book High chromium Ferritic and Martensitic Steels for Nuclear Applications written by R. L. Klueh and published by ASTM International. This book was released on 2001-01-01 with total page 221 pages. Available in PDF, EPUB and Kindle. Book excerpt: This monograph reviews the development of high-chromium ferritic/martensitic steels for exposure to the high-energy neutron environment of a fission or fusion reactor, and considers their potential use as a component material. The basic properties of the steels under non-nuclear conditions are provi