Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Microstructure Of Radiation Damage In The Uranium Film And Its Backing Materials Irradiated With 136 Mev 136xe26
Download Microstructure Of Radiation Damage In The Uranium Film And Its Backing Materials Irradiated With 136 Mev 136xe26 full books in PDF, epub, and Kindle. Read online Microstructure Of Radiation Damage In The Uranium Film And Its Backing Materials Irradiated With 136 Mev 136xe26 ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Microstructure of Radiation Damage in the Uranium Film and Its Backing Materials Irradiated with 136 MeV 136Xe26 by : Supriyadi Sadi
Download or read book Microstructure of Radiation Damage in the Uranium Film and Its Backing Materials Irradiated with 136 MeV 136Xe26 written by Supriyadi Sadi and published by . This book was released on 2012 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructure changes in uranium and uranium/metal alloys due to radiation damage are of great interest in nuclear science and engineering. Titanium has attracted attention because of its similarity to Zr. It has been proposed for use in the second generation of fusion reactors due to its resistance to radiation-induced swelling. Aluminum can be regarded as a standard absorbing material or backing material for irradiation targets. Initial study of thin aluminum films irradiation by 252Cf fission fragments and alpha particles from source has been conducted in the Radiation Center, Oregon State University. Initial study of thin aluminum films irradiation by 252Cf fission fragments and alpha particles from source has been conducted in the Radiation Center, Oregon State University. Aluminum can be regarded as a standard absorbing material or backing material for irradiation targets. The AFM investigation of microstructure damages of thin aluminum surfaces revealed that the voids, dislocation loops and dislocation lines, formed in the thin aluminum films after bombardment by 252Cf fission fragments and alpha particles, depends on the irradiation dose. The void swelling and diameter and depth of voids increase linearly with the fluence of particles and dose; however, the areal density of voids decreased when formation of dislocation loops began. Study of deposition of uranium on titanium backing material by molecular plating and characterization of produced U/Ti film has been performed. The U/Ti film has smooth and uniform surfaces but the composition of the deposits is complex and does not include water molecules which probably involve the presence of U (VI). A possible structure for the deposits has been suggested. X-ray diffraction pattern of U/Ti films showed that The U/Ti film has an amorphous structure. Uranium films (0.500 mg/cm2) and stack of titanium foils (thickness 0.904 mg/cm2) were used to study the microstructural damage of the uranium film and its backing material. Irradiation of U/Ti film and Ti foils with 1 MeV/u (136 MeV) 136Xe26 ions in was performed in the Positive Ion Injector (PII) unit at the Argonne Tandem Linear Accelerator System (ATLAS) Facility at Argonne National Laboratory, IL. Pre- and post- irradiation of samples was analyzed by X-ray diffraction, Scanning Electron Microscopy/Energy Dispersive Spectroscopy (SEM/EDS) and Atomic Force Microscopy (AFM). The irradiation of U/Ti films results in the formation of a crystalline U4O9 phase and polycrystalline Ti phase. Annealing of the thin uranium deposit on a titanium backing at 800°C in the air atmosphere condition for an hour produced a mixture of UO3, U3O, Ti, TiO and TiO2 (rutile) phases; meanwhile, annealing at 800°C for an hour in the argon environment produced a mixture of [beta]-U3O--, Ti and TiO2 (rutile) phases. These phenomena indicate that the damage during irradiation was not due to foil heating. Microstructural damage of irradiated uranium film was dominated by void and bubble formation. The microstructure of irradiated titanium foils is characterized by hillocks, voids, polygonal ridge networks, dislocation lines and dislocation networks. Theory predicts that titanium undergoes an allotropic phase transformation at 882.5 °C, changing from a closed-packed hexagonal crystal structure ([alpha]-phase) into a body-centered cubic crystal structure ([beta]-phase). When the titanium foils were irradiated with 136MeV 136Xe26 at beam intensity of 3 pnA corresponding to 966°C, it was expected that its structure can change from hexagonal-close packed (hcp) to body-centered cubic (bcc). However, in contrast to the theory, transformation from [alpha]-Ti (hcp) phase to fcc-Ti phase was observed. This phenomenon indicates that during irradiation with high energy and elevated temperature, the fcc-Ti phase more stable than the hcp-Ti Phase.
Book Synopsis Effects of Radiation on Materials by : H. R. Brager
Download or read book Effects of Radiation on Materials written by H. R. Brager and published by ASTM International. This book was released on 1982 with total page 786 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by :
Download or read book Effects of Radiation on Materials written by and published by ASTM International. This book was released on with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Damage in Materials by : Yongqiang Wang
Download or read book Radiation Damage in Materials written by Yongqiang Wang and published by MDPI. This book was released on 2020-12-28 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: The complexity of radiation damage effects in materials that are used in various irradiation environments stems from the fundamental particle–solid interactions and the subsequent damage recovery dynamics after the collision cascades, which involves multiple length and time scales. Adding to this complexity are the transmuted impurities that are unavoidable from accompanying nuclear processes. Helium is one such impurity that plays an important and unique role in controlling the microstructure and properties of materials used in fast fission reactors, plasma-facing and structural materials in fusion devices, spallation neutron target designs, actinides, tritium-containing materials, and nuclear waste. Their ultra-low solubility in virtually all solids forces He atoms to self-precipitate into small bubbles that become nucleation sites for further void growth under radiation-induced vacancy supersaturations, resulting in material swelling and high-temperature He embrittlement, as well as surface blistering under low-energy and high-flux He bombardment. This Special Issue, “Radiation Damage in Materials—Helium Effects”, contains review articles and full-length papers on new irradiation material research activities and novel material ideas using experimental and/or modeling approaches. These studies elucidate the interactions of helium with various extreme environments and tailored nanostructures, as well as their impact on microstructural evolution and material properties.
Book Synopsis Effects of Radiation on Materials by : Arvind S. Kumar
Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Effects of Irradiation on the Tensile Properties of Uranium by : R. E. Hueschen
Download or read book The Effects of Irradiation on the Tensile Properties of Uranium written by R. E. Hueschen and published by . This book was released on 1955 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials and Components by : John Frederick Kircher
Download or read book Effects of Radiation on Materials and Components written by John Frederick Kircher and published by . This book was released on 1964 with total page 714 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Effects in Materials by : Waldemar Alfredo Monteiro
Download or read book Radiation Effects in Materials written by Waldemar Alfredo Monteiro and published by BoD – Books on Demand. This book was released on 2016-07-20 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: The study of radiation effects has developed as a major field of materials science from the beginning, approximately 70 years ago. Its rapid development has been driven by two strong influences. The properties of the crystal defects and the materials containing them may then be studied. The types of radiation that can alter structural materials consist of neutrons, ions, electrons, gamma rays or other electromagnetic waves with different wavelengths. All of these forms of radiation have the capability to displace atoms/molecules from their lattice sites, which is the fundamental process that drives the changes in all materials. The effect of irradiation on materials is fixed in the initial event in which an energetic projectile strikes a target. The book is distributed in four sections: Ionic Materials; Biomaterials; Polymeric Materials and Metallic Materials.
Book Synopsis Effects of Radiation on Materials by : D. S. Gelles
Download or read book Effects of Radiation on Materials written by D. S. Gelles and published by ASTM International. This book was released on 1996 with total page 1169 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Damage in Nanostructured Metallic Films by : Kaiyuan Yu
Download or read book Radiation Damage in Nanostructured Metallic Films written by Kaiyuan Yu and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High energy neutron and charged particle radiation cause microstructural and mechanical degradation in structural metals and alloys, such as phase segregation, void swelling, embrittlement and creep. Radiation induced damages typically limit nuclear materials to a lifetime of about 40 years. Next generation nuclear reactors require materials that can sustain over 60 - 80 years. Therefore it is of great significance to explore new materials with better radiation resistance, to design metals with favorable microstructures and to investigate their response to radiation. The goals of this thesis are to study the radiation responses of several nanostructured metallic thin film systems, including Ag/Ni multilayers, nanotwinned Ag and nanocrystalline Fe. Such systems obtain high volume fraction of boundaries, which are considered sinks to radiation induced defects. From the viewpoint of nanomechanics, it is of interest to investigate the plastic deformation mechanisms of nanostructured films, which typically show strong size dependence. By controlling the feature size (layer thickness, twin spacing and grain size), it is applicable to picture a deformation mechanism map which also provides prerequisite information for subsequent radiation hardening study. And from the viewpoint of radiation effects, it is of interest to explore the fundamentals of radiation response, to examine the microstructural and mechanical variations of irradiated nanometals and to enrich the design database. More importantly, with the assistance of in situ techniques, it is appealing to examine the defect generation, evolution, annihilation, absorption and interaction with internal interfaces (layer interfaces, twin boundaries and grain boundaries). Moreover, well-designed nanostructures can also verify the speculation that radiation induced defect density and hardening show clear size dependence. The focus of this thesis lies in the radiation response of Ag/Ni multilayers and nanotwinned Ag subjected to charged particles. The radiation effects in irradiated nanograined Fe are also investigated for comparison. Radiation responses in these nanostructured metallic films suggest that immiscible incoherent Ag/Ni multilayers are more resistant to radiation in comparison to their monolithic counterparts. Their mechanical properties and radiation response show strong layer thickness dependence in terms of radiation hardening and defect density. Coherent twin boundaries can interact with stacking fault tetrahedral and remove them effectively. Twin boundaries can actively absorb radiation induced defects and defect clusters resulting in boundary migration. Size dependence is also found in nanograins where fewer defects exhibit in films with smaller grains. The electronic version of this dissertation is accessible from http://hdl.handle.net/1969.1/149359
Book Synopsis Radiation Damage in Reactor Materials by :
Download or read book Radiation Damage in Reactor Materials written by and published by . This book was released on 1963 with total page 784 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Rolling and Heat Treatment on Anisotropic Irradiation Growth of Uranium by : J. H. Kittel
Download or read book Effects of Rolling and Heat Treatment on Anisotropic Irradiation Growth of Uranium written by J. H. Kittel and published by . This book was released on 1961 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: An investigation was made to determine the effect of rolling temperature, roll pass design, amount of reduction, and heat treatment before and after rolling on the anisotropic growth rate of uranium under irradiation. The growth rate was found to increase with decreasing rolling temperature and with increasing reduction of area at 300 deg C. The rate of elongation was proportional to the amount of (010) component present or, where shortening occurred, to the amount of (100) component. Oval-edge-oval roll passes resulted in somewhat higher irradiation growth rates than did round roll passes. Recrystallization after rolling effectively reduced the irradiation growth rate of uranium rolled at temperatures of 500 deg C and lower. Irradiation caused length shortening in uranium which was beta quenched after being round-rolled at temperatures of 400 deg C and above, and which was beta quenched after being oval- rolled at temperatures of 300 deg C and above.
Book Synopsis Radiation Damage in Materials by : Yongqiang Wang
Download or read book Radiation Damage in Materials written by Yongqiang Wang and published by . This book was released on 2020 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: The complexity of radiation damage effects in materials that are used in various irradiation environments stems from the fundamental particle-solid interactions and the subsequent damage recovery dynamics after the collision cascades, which involves multiple length and time scales. Adding to this complexity are the transmuted impurities that are unavoidable from accompanying nuclear processes. Helium is one such impurity that plays an important and unique role in controlling the microstructure and properties of materials used in fast fission reactors, plasma-facing and structural materials in fusion devices, spallation neutron target designs, actinides, tritium-containing materials, and nuclear waste. Their ultra-low solubility in virtually all solids forces He atoms to self-precipitate into small bubbles that become nucleation sites for further void growth under radiation-induced vacancy supersaturations, resulting in material swelling and high-temperature He embrittlement, as well as surface blistering under low-energy and high-flux He bombardment. This Special Issue, “Radiation Damage in Materials--Helium Effects”, contains review articles and full-length papers on new irradiation material research activities and novel material ideas using experimental and/or modeling approaches. These studies elucidate the interactions of helium with various extreme environments and tailored nanostructures, as well as their impact on microstructural evolution and material properties.
Book Synopsis Radiation Damage in Metals by : N. L. Peterson
Download or read book Radiation Damage in Metals written by N. L. Peterson and published by . This book was released on 1976 with total page 430 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Effects in Solids by : Kurt E. Sickafus
Download or read book Radiation Effects in Solids written by Kurt E. Sickafus and published by Springer Science & Business Media. This book was released on 2007-05-22 with total page 593 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is a comprehensive overview of fundamental principles and relevant technical issues associated with the behavior of solids exposed to high-energy radiation. These issues are important to the development of materials for existing fission reactors or future fusion and advanced reactors for energy production; to the development of electronic devices such as high-energy detectors; and to the development of novel materials for electronic and photonic applications.
Book Synopsis Radiation Damage to Graphite from 30 C to 185 C by : R. E. Nightingale
Download or read book Radiation Damage to Graphite from 30 C to 185 C written by R. E. Nightingale and published by . This book was released on 1957 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Damage on Multiple Length Scales in Uranium Dioxide by :
Download or read book Radiation Damage on Multiple Length Scales in Uranium Dioxide written by and published by . This book was released on 2015 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation damage in UO2 has been well studied but there exists little correlation between point defect accumulation, lattice structure changes and microstructure. This is partly because irradiated nuclear fuel is highly radioactive and its defect chemistry is extremely complicated resulting from fission of the material and consequent fission products being embedded in the fuel matrix [Olander1976]. To adequately study the evolution of defects from point defects through to microstructure features, the resulting defects have to be intentionally simplified for characterization. Ion accelerators have the unique capability of creating simple microstructure features using specific ions, without the added complication of fission and neutron activation from nuclear reactors. As an example, H+ ions have been used to create (only) a distribution of dislocations that were studied using various techniques. The ability to tune the energy or type of the ion to achieve desirable implantation depth and ideally simple microstructure renders it a lucrative instrument for this type of analysis. X-ray diffraction (XRD) studies and transmission electron microscopy (TEM) have been utilized to study extended structure changes and microstructure evolution. Ion beam irradiations create displacements and displacement networks, voids, surface fracturing, gas bubbles and several other microstructure changes to model nuclear reactor damage [Noris1972]. Using an ion accelerator, it has been possible to isolate these radiation induced defects and study their subsequent evolution with increasing dose. Insofar, since all of the phenomena caused by radiation damage originate from point defects, the elucidation of radiation effects on the atomic scale is crucial. This is rendered complicated due to aperiodic irradiation defects. This lack of periodicity renders standard approaches, such as TEM and XRD ineffective, as these methods probe average structure over tens of Angstroms. Therefore, techniques that are sensitive to short range order are required to understand the defect detail on atomic scale. X-ray absorption fine structure spectroscopy (XAFS) measures the population-weighted local structure and chemical speciation of the examined elements making it perhaps the most incisive method for determining the local range order in irradiated materials. In this study, Extended X-ray Absorption Fine Structure (EXAFS) measurements have shed significant insight into the local chemistry evolution from irradiation damage in UO2. With the aforementioned defect characterization techniques, this project has developed three significant scientific conclusions: 1. Irradiation of UO2 creates changes with some similarity to oxidation, but the increase in lattice parameter (as compared to oxidation) indicates differences in microstructure. 2. TEM invisible defect clusters are predominantly responsible for lattice structure changes in UO2, confirmed using EXAFS and Cluster Dynamics simulation. 3. The combination of EXAFS, Cluster Dynamics, CrystalMaker Analysis, MD and Raman measurements support the existence of hyper and hypo-stoichiometric regions in the material after irradiations. 4. The lattice parameter, the microstructure visible to TEM and the lattice structure invisible to TEM all scale with DPA.
