Download or read book Voids in Neutron irradiated Metals and Alloys written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Small-angle x-ray and neutron scattering are powerful analytical tools for investigating long-range fluctuations in electron (x-rays) or magnetic moment (neutrons) densities in materials. In recent years they have yielded valuable information about voids, void size distributions, and swelling in aluminum, aluminum alloys, copper, molybdenum, nickel, nickel-aluminum, niobium and niobium alloys, stainless steels, graphite and silicon carbide. In the case of aluminum, information concerning the shape of the voids and the ratio of specific surface energies was obtained. The technique of small-angle scattering and its application to the study of voids is reviewed in the paper. Emphasis is placed on the conditions which limit the applicability of the technique, on the interpretation of the data, and on a comparison of the results obtained with companion techniques such as transmission electron microscopy and bulk density. 8 figures, 41 references.

Download or read book The Growth and Coalescence of Voids in Irradiated Metals written by Louis Kenneth Mansur and published by . This book was released on 1974 with total page 270 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Irradiation of Pure Metals and Aluminum zinc Alloys written by James Albert Horak and published by . This book was released on 1966 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Void Formation in Neutron Irradiated Metals written by and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Microstructure of Neutron Irradiated Vanadium Alloys written by H. Kinoshita and published by . This book was released on 1990 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: To investigate the effect of alloying elements on void formation and precipitation during neutron irradiation, vanadium and vanadium based alloys were irradiated in the experimental fast breeder reactor "JOYO" up to 6 x 1025 n/m2 at 670 to 870 K. Alloying elements were selected on the basis of volume size factors: carbon for an interstitial atom, chromium for an undersized substitutional atom and titanium and molybdenum are oversized ones. Voids were formed in all materials except in V-Ti alloys. The V-Cr alloy shows inhomogeneous void formation, and the swelling was larger compared to other alloys. The void formation was related to the radiation-induced precipitates which nucleated on dislocations. In the matrix of the V-Mo alloy, the precipitation was not confirmed, and homogeneous void formation occurred so the swelling was not large. Void formation and precipitation are discussed on the basis of alloying effects.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book VOID DAMAGE IN NEUTRON IRRADIATED STRUCTURAL METALS written by and published by . This book was released on 1972 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by and published by ASTM International. This book was released on 1973 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium Base Alloys written by DJ. Michel and published by . This book was released on 1979 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microstructure and microhardness of niobium and commercial prototype niobium-base alloys have been investigated following fast neutron irradiation to a fluence of 1.1 x 1022 neutrons (n)/cm2 (0.1 MeV), 4 displacements per atom (dpa), at 482°C. The purpose of this work was to determine the effects of molybdenum and zirconium alloy additions on the resistance of niobium-base alloys to neutron irradiation. Neutron irradiation of the niobium and Nb-1Mo alloy produced very small voids whose mean diameters were in the range of 30 to 35 Å. In all other alloys, however, no voids were observed and the principal effect of the neutron irradiation was to form a high density of 30 to 40 Å diameter dislocation loops which are believed to be primarily of interstitial character. The effect of fast neutron irradiation was to increase the microhardness of both niobium and all its alloys, with the largest increase in the Nb-1Zr alloy and the smallest increase in the ternary Nb-5Mo-1Zr alloy. Previous work on niobium and Nb-1Zr alloy has shown that a vacancy trapping mechanism is particularly effective at irradiation temperatures up to 600°C for fast neutron fluences of 2.5 x 1022 n/cm2 (0.1 MeV). The observation from the present experiments that molybdenum and zirconium additions were effective in the suppression of void formation suggests that a vacancy trapping mechanism was operative in the present alloys. The smaller hardness increase observed for the ternary alloys suggests that these alloys may maintain good engineering properties in addition to their improved resistance to void formation.

Download or read book Dependence of Void Formation on Phase Stability in Neutron Irradiated Type 316 Stainless Steel written by HR. Brager and published by . This book was released on 1979 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: The void swelling rate in Type 316 steel is dominated by the instantaneous composition of the austenite matrix rather than by the concurrent nature of the dislocation and void microstructure alone. This is the conclusion derived from a series of neutron-irradiation experiments designed to determine which microstructural components account for the variability of void development observed in this alloy in response to changes in composition, preirradiation treatment, and irradiation history. The attainment of steady-state swelling is thought to be related to the development of a saturation microstructure of precipitates and dislocations. The existence of a saturation state for dislocation microstructure has been confirmed, but this condition is reached at fluences substantially below the onset of steady-state swelling. Relative to a solution-annealed treatment, 20 percent cold working accelerates the approach to saturation of the dislocation microstructure; thus the delay of swelling by cold work cannot be rationalized simply in terms of the time or fluence dependence of dislocation density.

Download or read book Effects of Damage Rate on Formation of Voids and Dislocation Loops in Metals written by T. Yoshiie and published by . This book was released on 2000 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Effects of damage rate on the formation of voids and interstitial type dislocation loops in pure metals, such as Au, Cu, Ni, Fe and V, and alloys of Ni and V, were investigated. The specimens were irradiated at the Kyoto University Reactor (KUR) with improved temperature control. The dose rates of neutron irradiation were 4.4x1015n/m2s (E > 0.1 MeV) and 3.9x1017 n/m2s (E > 0.1 MeV) at 573 K. By the total dose of about 7x1021 n/m2 (E > 0.1 MeV), the loop density increased with increasing dose rate, whereas the growth behavior of microvoids depended on the dose rate and irradiated materials. In Cu, Fe and V, the concentration and the size of microvoids increased with increasing dose rate. In Au, the difference of microvoid formation between two dose rates was small. While in Ni, Ni-Cu and Ni-Ge, the size of microvoids increased with decreasing dose rate. The behaviors of formation of microvoids and dislocation loops were analyzed by the rate theory. It was clarified that the microvoid formation strongly relates to the mobility of vacancies. The calculation also showed that the nucleation of dislocation loops increases with increasing dose rate.

Download or read book High Dose Effects in Neutron Irradiated Face centered Cubic Metals written by and published by . This book was released on 1993 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt: During neutron irradiation, most face-centered cubic metals and alloys develop saturation or quasi-steady state microstructures. This, in turn, leads to saturation levels in mechanical properties and quasi-steady state rates of swelling and creep deformation. Swelling initially plays only a small role in determining these saturation states, but as swelling rises to higher levels, it exerts strong feedback on the microstructure and its response to environmental variables. The influence of swelling, either directly or indirectly via second order mechanisms, such as elemental segregation to void surfaces, eventually causes major changes, not only in irradiation creep and mechanical properties, but also on swelling itself. The feedback effects of swelling on irradiation creep are particularly complex and lead to problems in applying creep data derived from highly pressurized creep tubes to low stress situations, such as fuel pins in liquid metal reactors.

Download or read book Neutron Irradiation Damage in a Precipitation Hardened Aluminum Alloy written by K. Farrell and published by . This book was released on 1973 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: A 6061 aluminum alloy target sleeve from the high flux isotope reactor, originally in a precipitation-hardened condition, was examined for neutron radiation damage after exposure to a maximum fast fluence of 9.2 x 1022 n/cm2 (E > 0.1 MeV) and a thermal fluence of 1.38 x 1023 n/cm2 at 60 C (140 F). Voids and a transmutation-produced silicon precipitate were found to cause about 1.1 percent internal swelling; a surface oxide scale contributed additional swelling. Irradiation-induced strength increases were measured at test temperatures in the range 25 to 200 C (77 to 392 F) and are accounted for in terms of the observed silicon precipitate and an associated dislocation structure. There was also a loss of ductility that was most severe at 200 C. The fracture mode appeared to remain transgranular over the range of test temperatures.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-02 with total page 484 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Metals Abstracts written by and published by . This book was released on 1989 with total page 1266 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Neutron Irradiation in Non fissionable Metals and Alloys written by and published by . This book was released on 1962 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: