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Saturday, April 18, 2020 | History

2 edition of use of ion beams in the study of the oxidation of Zirconium found in the catalog.

use of ion beams in the study of the oxidation of Zirconium

L. Weidman

use of ion beams in the study of the oxidation of Zirconium

dissertation [presented for the] M.Sc. Degree in AppliedSolid State Physics.

by L. Weidman

  • 273 Want to read
  • 13 Currently reading

Published by Brighton Polytechnic, Department of Applied Physics in Brighton .
Written in English


Edition Notes

ContributionsBrighton Polytechnic. Department of Applied Physics.
ID Numbers
Open LibraryOL13744053M

  Hydrogen sorption, structural phase state and mechanical properties after hydrogenation of zirconium alloy Zr1%Nb with ZrO2 and TiO2 coatings were investigated. It has been established that ZrO2 coating reduces the rate of hydrogen sorption by zirconium alloy Zr1%Nb in comparison with the initial material at hydrogen saturation temperature °: Ivan P. Chernov, Natalia S. Pushilina, Viktor N. Kudiiarov, Ekaterina V. Berezneeva, Aleksandra N. N. The thickness or weight change in oxide scale with time is generally used to assess oxidation rates of the metallic alloys. In a linear or parabolic growth rate, the mixed para-linear kinetics is widely accepted to deal with the short-time growth of Author: Xianglong Yu, Ji Zhou. Use the Tyndall effect to explain why it is difficult to drive through fog using high beams instead of low beams. Fog is a colloid which disperses light that shines through it. Because high beams shine straight ahead and further down the road more of the light is able to be scattered and reflected back towards the driver. Zirconium dioxide (ZrO 2), sometimes known as zirconia (not to be confused with zircon), is a white crystalline oxide of most naturally occurring form, with a monoclinic crystalline structure, is the mineral baddeleyite.A dopant stabilized cubic structured zirconia, cubic zirconia, is synthesized in various colours for use as a gemstone and a diamond ance: white powder.


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use of ion beams in the study of the oxidation of Zirconium by L. Weidman Download PDF EPUB FB2

A comparison between two zirconium oxidation experiments under heavy ion irradiation performed in the same temperature and pressure conditions is presented.

In the first experiment, a 6 μm thick zirconium foil is irradiated with a 50 MeV Xe beam which stops in the Zr foil. Finally, the use of ion beam techniques to study iodine diffusion and release from hulls is an interesting tool.

It allows us to extrapolate diffusion coefficients in conditions of geological disposal. At 50°C, the thermal diffusion coefficient is found to be 10 −31 cm 2 s −1 for stable iodine. We aim to determine this coefficient under Cited by: 4. Request PDF | Diffusion study of implanted iodine in zirconium using ion beams | This study is related to the back end of the nuclear fuel cycle.

During nuclear reactor operation, the inner side. High resolution secondary ion mass spectrometry (SIMS) analysis has been used to study the oxidation mechanisms when commercial low tin ZIRLO™ 1 and Zircaloy 4 materials are exposed to corroding environments containing both 18 O and 2 H by: Study of oxidation mechanisms of zirconium alloys by electron microscopy Abstract: The current work is part of the EPSRC MUZIC project, which established the collaboration among several universities to carry out a multidiscipline study on the breakaway oxidation of zirconium by:   A study of the oxidation of zirconium in oxygen and water vapor in the temperature range of – °C has shown that oxidation occurs in a series of stages.

In the first oxidation stage, a thin film is formed with the definite texture of a cubic modification and possessing high by: 5. The study of high temperature oxidation of zirconium and zircaloy is now classical but deserves to be continued.

New alloys are still developed. For instance, to limit the growth of zirconium oxide on fuel claddings, niobium-rich zircaloys seems to be efficient, thanks to the reduction of the amount of quadratic ZrO 2, responsible for the formation of the by:   The oxidation of the material simulates material degradation in elevated temperature oxidative environments with the formation of surface oxide layers on zirconium-silicide structural components.

Ion irradiation provided data on the radiation stability of these surface oxide by: 2. comments to all of the chapters of the book. Their primary responsibilities for the different sections/chapters were divided as follows.

Paul Brown prepared the introduction, and the sections on elemental zirconium, the zirconyl ion, the gaseous zirconium oxides, zirconium hydride, the halogen compounds and complexes, the. tion were prepared using focused ion beam equipment. To investigate differences in the oxide properties between Zircaloy-4 and the Si-coated layer, cross-sectional analyses using SEM and TEM were.

Abstract. I have tried to summarize the oxidation behavior of zirconium and its alloys in both gaseous and aqueous environments, and to show how other environments, such as liquid metals, can be considered as special cases of one or other of the main by: Thin zirconium oxide films were grown using the ion-beam assisted deposition method.

Zirconium metal was evaporated by an electron beam and condensed on a Si substrate, while oxygen ions were directed simultaneously onto the substrate, allowing the fundamental deposition parameters of ion energy and arrival rate ratio ARR(O/Zr) to be measured and.

Zirconium-based alloys have long been used as nuclear fuel cladding, due to their resistance to corrosion and low neutron cross section. In particular, the Zircaloy series of alloys have been the most widely implemented in reactors, with much attention focused on the oxidation behavior of Zircaloy-2 and ZircaloyCited by: Non-equilibrium oxidation states of zirconium during early stages of metal oxidation Wen Ma,1 F.

William Herbert,1,2 Sanjaya D. Senanayake,3 and Bilge Yildiz1,a) 1Laboratory for Electrochemical Interfaces, Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, MassachusettsUSA.

Oxidation of ion-alloyed samples of alloys. During oxidation of samples of zirconium and its alloys in the above-mentioned time intervals, the part of samples was withdrawn from ampoules to determine the thickness of oxide films and subsequently study their structural-phase state. Hanlon S.M., Persaud S.Y., Long F., Daymond M.R.

() Advanced Characterization of Hydrides in Zirconium Alloys. In: Jackson J., Paraventi D., Wright M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water by: 2.

In this paper, the influence of plasma immersion titanium implantation into the zirconium alloy Zr-1Nb on the oxidation behavior at ° C for 5, 24, 72.

Oxidation and diffusion study on AlCrVN hard coatings using oxygen isotopes 16O and 18O Article in Thin Solid Films April with 57 Reads How we measure 'reads'.

Zirconium carbide oxidation: Kinetics and oxygen diffusion through the intermediate layer Claudia Gasparrini1 interface with a Focused Ion Beam instrument coupled with a Secondary Ion Mass Spectrometer (FEI FIBSIMS; FEI Company, Hillsboro, OR).

This microscope uses aCited by: 8. Thin zirconium oxide films were grown using the ion‐beam assisted deposition method. Zirconium metal was evaporated by an electron beam and condensed on a Si substrate, while oxygen ions were directed simultaneously onto the substrate, allowing the fundamental deposition parameters of ion energy and arrival rate ratio ARR(O/Zr) to be measured and controlled by: In order to study the influence of lanthanum ion implantation on the oxidation behavior, zirconium specimens were implanted at a dose range.

Zirconium is a chemical element with the symbol Zr and atomic number The name zirconium is taken from the name of the mineral zircon, the most important source of zirconium.

It is a lustrous, grey-white, strong transition metal that closely resembles hafnium and, to a lesser extent, titanium. Zirconium is mainly used as a refractory and opacifier, although small amounts are used Pronunciation: /zərˈkoʊniəm/ ​(zər-KOH-nee-əm).

oxidation of cladding materials [4]. Increasing the production of hydrogen due to zirconium oxidation by high-temperature steam is one of the areas currently being study to make fuel systems inherently safer in the accidents situations, especially after what happened in Fukishma Daichii Reactor [5].

TheAuthor: Mamoun I. Sagiroun, Cao Xinrong. The ion beam has a number of other uses as well, including the deposition of material from a gaseous layer above the sample.

Most of the recent commercial FIB systems and dual-beam platforms use gallium (Ga +) as the ion source. The reason for preferring gallium element as the ion source is explained in the subsequent by: 3. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency, is water corrosion.

This oxidation process has recently been linked to the presence of a sub-oxide phase with well-defined composition but unknown structure at the metal–oxide by: In this reaction zirconium is produced by the reduction of zirconium tetrachloride with an active metal such as magnesium at – °C.

Elsewhere in the literature, the preparation of metallic Zr nanoparticles by ultrafast laser ablation of a zirconium rod Cited by:   Higher nitrides of hafnium, zirconium, and titanium synthesized by dual ion beam deposition - Volume 1 Issue 3 - B.O.

Johansson, H.T.G. Hentzell, J.M.E. Harper, J.J. Cuomo Skip to main content We use cookies to distinguish you from other users and to provide you with a better experience on our by: Zirconium oxidation was investigaied in the temperature range io deg C at oxygen pressures of 50,and mm.

The reaction rate of massive (parallelepiped) samples was best expressed by the cubic rate law. Zirconium (Zr), chemical element, metal of Group 4 (IVb) of the periodic table, used as a structural material for nuclear reactors. atomic number 40 atomic weight melting point 1, °C (3, °F) boiling point 3, °C (6, °F) specific gravity at 20 °C (68 °F) oxidation.

Zirconia was prepared at low temperatures (zirconium carboxylates where the R groups were systematically varied. The combination of density functional theory (DFT) calculations and extensive characterization of the precursors (i.e., X-ray diffraction, thermal gravimetric analysis, infrared spectroscopy, and Cited by: 4.

journal article: study of the oxidation of non-alloyed zirconium and of oxygen diffusion in the oxide film and in the metal. study of the oxidation of non-alloyed zirconium and of oxygen diffusion in the oxide film and in the metal (in french) full record; other related research.

During the study, metal leaching was one of the main problems in the liquid phase oxidation of cyclohexane because the impregnation, ion-exchange, or isomorphous substitution cannot form strong bonding between the metal species and the support [24,25,26].Author: Yuechao Hong, Jie Peng, Zhichao Sun, Zhiquan Yu, Anjie Wang, Yao Wang, Ying-Ya Liu, Fen Xu, Li-Xian.

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Challenges to the use of ion irradiation for emulating reactor irradiationCited by: First-principles study of the surfaces of zirconium during early stages of metal oxidation by ===== Submitted to the Department of Nuclear Science and Engineering in partial ful llment of the requirements for the degree of Bachelor of Science in Nuclear Science and Engineering at the Massachusetts Institute of Technology June c.

Mechanism of ion exchange in zirconium phosphates. Refinement of the crystal structure -zirconium phosphateCited by: Formation of thermodynamically stable dications in the gas phase by thermal ion-molecule reactions: tantalum(2+) and zirconium(2+) with small alkanes Gas-Phase Oxidation Reactions of Ta2+: Synthesis and Properties of TaO2+ and TaO22+.

A Combined Guided Ion Beam and DFT Study. Journal of the American Chemical SocietyCited by: M. Ayanoglu, A.T. Motta "In-situ study: Faulted loop and void behavior in single beam bulk irradiated FeCrNi model alloy", Transactions of the American Nuclear Society, vp, Transactions of the American Nuclear Society, ANS Highly reduced organometallics of the Group IV elements: Part One.

The study of (trmpe) metal tetracarbonyl complexes of titanium, zirconium, and hafnium. Part Two. The study of bis-arene titanium complexes prepared from arene radical anions.

The deformation kinetics of zirconium and Zircaloy-2 strips, resulting from oxidation at °C in dry oxygen, were measured as a function of time. The stress distribution in the oxidized specimens was analyzed using a stress model based on the theory of elasticity and was correlated with the oxidation kinetics.

The magnitude of the stress generated during oxidation Cited by: @article{osti_, title = {Chemistry of organo-zirconium and -hafnium compounds}, author = {Cardin, D.J.

and Lappert, M.F. and Raston, C.L.}, abstractNote = {The authors have managed to pull together, in remarkably comprehensive fashion, the organometallic chemistry of zirconium and hafnium, but they have done so not simply in an.

@article{osti_, title = {Electron beam evaporation of molybdenum, yttrium and zirconium targets for heavy-ion nuclear physics}, author = {Greene, J P and Thomas, G E}, abstractNote = {Self-supporting targets of {98}Mo, Y and {sup 90}Zr with thickness of and {mu}g/cm{sup 2} were prepared by electron beam gun evaporation.

Oxidation and crystallization of an amorphous Zr60Al15Ni25 alloy - Volume 11 Issue 11 - X. Sun, S. Schneider, U. Geyer, W. L. Johnson, M-A. Nicolet Skip to main content We use cookies to distinguish you from other users and Cited by: For each compound, a formal oxidation number for zirconium is given, but the usefulness of this number is limited for p-block elements in particular.

Based upon that oxidation number, an electronic configuration is also given but note that for more exotic compounds you should view this as a guide only.