bluuebunny/crossref_metadata_2025_split huggingface dataset:
The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
Authors: Dahlbäck M , Limbäck M , Hallstadius L , Barberis P , Bunel G , Simonot C , Andersson T , Askeljung P , Flygare J , Lehtinen B , Massih AR 
Published: August 2005

Abstract
The effect of β-quenching performed in the final size of Zircaloy-4 guide tubes and Zircaloy-2 sheets during fabrication process on the products' mechanical properties, crystallographic texture, microstructure, and corrosion behavior has been investigated and presented in this paper. Moreover, the impact of this processing on the irradiation growth of pressurized water reactor Zircaloy-4 guide tubes in a test reactor and Zircaloy-2 fuel channels in boiling water reactors has been evaluated. The results indicate that the irradiation growth rates of the final dimension β-quenched (FDBQ) products are substantially lower than those fabricated by conventional (Standard) techniques. BWR channels irradiated up to a fast neutron fluence of about 9 × 1025 m−2 maintain this low growth behavior. Corrosion properties of FDBQ products have been made similar to that of the Standard material by performing an α-annealing step after the β-quenching. The annealing temperature and annealing time have been optimized in order to obtain good corrosion resistance. In-reactor data on Zircaloy-2 channels irradiated to a fuel assembly exposure of about 50 MWd/kgU indicate similar corrosion performance for the FDBQ and Standard materials. Finally, the in-reactor data on Zircaloy-2 channels show that bowing of the FDBQ and Standard channels is comparable up to a fast neutron fluence of about 7 × 1025 m−2.
Shadow Corrosion Mechanism of Zircaloy
Authors: Lysell G , Nystrand A-C , Ullberg M 
Published: August 2005

Abstract
The mechanism of Zircaloy shadow corrosion was studied theoretically and experimentally. The theoretical study showed shadow corrosion, with a few exceptions, to be remarkably consistent with a galvanic corrosion mechanism. The exceptions may be explained as radiation effects. An experiment was therefore devised to test the galvanic hypothesis, based on the fact that galvanic corrosion requires a closed current loop. Three pieces of Zircaloy cladding with stainless steel counter electrodes were exposed in-pile. Two of the claddings were galvanically coupled to the counters. The third cladding was well insulated by fitting it to a 100 mm sapphire tube. The claddings were irradiated together in oxidizing water chemistry for one reactor period. The galvanically coupled claddings developed shadow corrosion, but not the well insulated cladding.
Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
Authors: Motta AT , Yilmazbayhan A , Comstock RJ , Partezana J , Sabol GP , Lai B , Cai Z 
Published: August 2005

Abstract
The structures of oxides formed in water and lithiated water on three Zr-based alloys with varied corrosion behavior were studied with micro-beam synchrotron radiation and optical microscopy. Micro-beam synchrotron radiation (0.2 μm spot) has a unique combination of high elemental sensitivity (ppm level) and fine spatial resolution that allowed the determination of various oxide characteristics such as phase content, texture, grain size, and composition as a function of distance from the oxide-metal interface.
Micro-beam X-ray fluorescence shows that the oxides formed in lithiated water have increased levels of Fe absorbed from the autoclave environment indicating greater oxide porosity in these oxides. The phase content, texture, and grain size of oxides were studied in detail using synchrotron radiation micro-beam diffraction for samples corroded in water and lithiated water. A remarkable periodicity was observed in the oxide structures using various techniques including X-ray peak intensities for both monoclinic and tetragonal zirconia, texture, and optical microscopy. The periods were similar to the transition period and were less visible in the oxides that behaved worse in lithiated water. These results are discussed in terms of models of oxide growth and of the differences between alloys.
Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
Authors: Griffiths M , Christodoulou N , Donohue SA 
Published: August 2005

Abstract
The diametral expansion and elongation rates of Zr-2.5Nb pressure tubes in CANDU™ (CANada Deuterium Uranium) nuclear reactors are important properties that limit their useful life and the maximum power level for reactor operation.
For a given set of operating conditions there is considerable variability in the deformation rates because of the variations in as-fabricated microstructure and chemistry from tube-to-tube — specifically grain size, crystallographic texture, and oxygen content. The as-fabricated microstructure also varies within a given tube, the largest variation occurring along the length, and this is a result of cooling of the tube during the extrusion process. During service in a nuclear reactor, the microstructure evolves further, and this additional change in microstructure is primarily dependent on the rate of radiation damage (determined by the fast neutron flux), the temperature, and the time. Both the fast neutron flux and temperature vary at all points within the pressure tube.
For a given material microstructure, the deformation is a function of the operating conditions: coolant pressure (stress), temperature, and neutron flux. In principle, the deformation rate is a linear function of fast neutron flux, and this is mostly true for fast neutron fluxes of the order of 1017 n.m−2.s−1. Recent analyses of data from pressure tubes measured over long periods of operation in reactor have shown that the steady-state diametral creep rates are not linear with fast neutron flux for fluxes up to about 0.5 × 1017 n.m−2.s−1. A qualitative model has been developed to account for the observed behavior based on the modifying effects of neutron flux and temperature on the microstructure. The model describes the suppression of thermal creep and the transition from thermal to irradiation creep with increasing neutron flux.
Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
Authors: Glendening A , Koss DA , Motta AT , Pierron ON , Daum RS 
Published: August 2005

Abstract
The fracture behavior of unirradiated Zircaloy-4 containing either solid hydride blisters or hydrided rims has been examined for the contrasting conditions of equal-biaxial and plane-strain tensile deformation at three temperatures (25°, 300°, and 375°C). Cold-worked and stress-relieved Zircaloy-4 sheet containing hydride blisters shows nearly identical failure strains in equal-biaxial and plane-strain tensile deformation for a wide range of blister or rim depths. In all cases, failure strains decrease rapidly with increasing hydride blister or rim thickness, especially in the ≤100 µm range. Test temperature has a significant effect on ductility with failure strains at 300° and 375°C being much greater than at room temperature. The results indicate that the ductility of material containing hydride rims/blisters greater than ≈ 30–40 µm deep is limited by crack growth, which occurs in a mode I manner at 25°C but in a mixed mode I/II manner at ≥300°C (and at higher failure strain levels).
The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
Authors: Dahlbäck M , Hallstadius L , Limbäck M , Vesterlund G , Andersson T , Witt P , Izquierdo J , Remartinez B , Diaz M , Sacedon JL , Alvarez A-M , Engman U , Jakobsson R , Massih AR 
Published: August 2005

Abstract
This paper focuses on the effect of liner component Fe content on cladding corrosion, hydriding and Pellet-Cladding Interaction (PCI) resistance. A multitude of experimental techniques is used to evaluate the various properties. The PCI resistance is evaluated through mandrel testing of un-irradiated claddings as well as by ramp tests of pre-irradiated fuel segments in the Studsvik R2 reactor. The results from the mandrel testing indicate that an increase of the iron concentration from 0.05 to 0.21 wt% has a rather small impact on the PCI properties. The ramp data, on the other hand, show a clear decrease in the PCI resistance as the Fe content approaches and exceeds 0.19 wt%. The phenomena involved in secondary degradation are complex, and separate tests are used to evaluate the corrosion resistance in steam as well as the hydriding resistance in pure hydrogen. The corrosion test includes cladding tubes with ZrSn-liner components with iron concentrations from 0.025 to 0.21 wt%. The results show that the corrosion resistance is dramatically increased as the Fe content is increased from 0.025 to 0.05–0.06 wt%, but that a further increase of the Fe concentration only has a minor impact on the corrosion resistance. However, increasing the Fe content from 0.05 to 0.21 wt% increases the hydrogen pick-up rate. The 0.21 wt% Fe liner has a significantly higher density of Secondary Phase Particles (SPPs) as well as slightly larger SPPs than the 0.05 wt% Fe liner. Consequently, it is believed that the SPPs offer sites where hydrogen can easily be absorbed into the Zr-based material, and the frequency of these sites is important for the hydrogen pick-up rate. It is finally concluded that even though the optimization of the Fe concentration in the liner is complex, an iron level regime exists that provides a good balance of resistance against PCI, corrosion, and hydriding.
Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
Authors: Desquines J , Cazalis B , Bernaudat C , Poussard C , Averty X , Yvon P 
Published: August 2005

Abstract
The PROMETRA material testing program is a support program related to the study of high burnup fuel rod behavior under Reactivity Initiated Accidents (RIA) and to the interpretation of the CABRI REP-Na RIA test results. Hoop and axial tensile tests have been performed on fresh and irradiated Zircaloy-4 cladding alloy first at CEA Grenoble hot labs and now at CEA Saclay in order to assess the cladding mechanical behavior during RIA transients. Efforts have been continuously carried out in order to improve the prototipicallity of the tests for RIA studies involving new specimens and new testing techniques. The corrosion level of irradiated specimens reached up to 130 μm of oxide layer thickness. The influence of in-pile oxide layer spallation has also been addressed. High strain-rate material properties of irradiated Zircaloy-4 and the consequences of hydride embrittlement can be derived from the PROMETRA program.
Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
Authors: Barberis P , Dupin N , Lemaignan C , Pasturel A , Grange JM 
Published: August 2005

AbstractTEM investigations in Zr-Fe and Zr-Fe-Ni, Zr-Ni-Cr and Zr-Cr-Fe systems were performed to assess the second particles present in these alloys, either in quasi equilibrium conditions, or after quenching and annealing experiments.At equilibrium, Zr3Fe was found to dissolve Ni up to 12 at%. Ab initio computations provided formation enthalpies for several Zr-Fe compounds and showed that the Zr2Fe is metastable at low temperature. All of these data allowed us to extend the thermodynamic database ZIRCOBASE; very good agreement between the thermodynamic computations and the experimental evidences was obtained.Quenching and annealing experiments showed that Zr2Fe is formed for low quenching rates, while Zr3Fe is formed for higher quenching rates.Last, corrosion results in various conditions show that the influence of second phase particles volume fraction depends on the corroding atmosphere.
Creation of Oxidized Zirconium Orthopaedic Implants
Authors: Hunter G , Dickinson J , Herb B , Graham R 
Published: August 2005

Abstract
More demanding performance expectations for total joint arthroplasty are driving the development of alternative bearing materials. Oxidized zirconium was developed as an alternative to cobalt-chromium alloy for knee and hip femoral components in order to reduce wear of the polyethylene counterface and to address the needs of metal-sensitive patients. Oxidation in high temperature air transforms the metallic Zr-2.5Nb alloy surface into a stable, durable, low-friction oxide ceramic without creating the risk for brittle fracture associated with monolithic ceramic components. This presentation reviews aspects of this technology with a historical perspective, including standards for the zirconium alloy, non-medical applications for oxidized zirconium, and previous orthopaedic applications for zirconium. Manufacturing processes for oxidized zirconium components are described, beginning with refining of the zirconium from beach sand, to producing the alloy ingot and bar, to fabricating the component shape, and finally to oxidizing the surface and burnishing it to a smooth finish. Conditions are described for producing the oxide with excellent integrity, which is nominally 5 µm thick and predominantly monoclinic phase. The metal and oxide microstructures are characterized and related to the mechanical properties of the components and durability of the oxide. Laboratory hip and knee simulator tests are reviewed, which indicate that oxidized zirconium components reduce wear of the polyethylene counterface by 40–90 % depending on test conditions. As evidenced by promising early clinical experience, oxidized zirconium components have characteristics that provide an alternative to conventional cobalt-chromium components with an interchangeable surgical technique, while providing the potential for superior performance.
Mechanical Properties of Cast Ti-Fe-O-N Alloys
Authors: Koike M , Guo Q , Brezner M , Fujii H , Okabe T 
Published: August 2005

Abstract
A recent addition to existing titanium alloys is the Super-TIX™ series (Nippon Steel Corp., Japan), which has intermediate strength between the strengths of CP Ti and Ti-6Al-4V as a result of balancing the Fe, O, and N concentrations. Two alloys in this series were investigated: Ti-1%Fe-0.35%O-0.01%N (Super-TIX800™; LN) and Ti-1%Fe-0.3%O-0.04%N (Super-TIX800N™; HN). These alloys were are-melted and cast using an investment casting method, and their mechanical properties were examined. The yield strength (∼600 MPa) and tensile strength (∼680 MPa) were approximately 33 and 29% higher, respectively, than the corresponding strength of cast CP Ti (ASTM Grade 2). Their percent elongation was somewhat (but not significantly) higher (2–3 %) than that of Ti-6A-4V. On the other hand, the elongation of CP Ti was approximately 7 %. The moduli of elasticity of the alloys ranged from 100–120 GPa. These Ti-Fe-O-N alloys exhibit higher uniaxial yield and tensile strengths than CP Ti, which is currently used for dental applications.
Comparison of Stress Corrosion Cracking Characteristics of CP Ti, Ti-6Al-7Nb, Ti-6Al-4V, and Ti-15Mo
Authors: Scott Williamson R , Roach MD , Zardiackas LD 
Published: August 2005

AbstractThe purpose of this research was to evaluate and compare the stress corrosion cracking (SCC) of Ti-15 Mo (ASTM F2066), Ti-6Al-7Nb (ASTM1295), Ti-6Al-4V ELI (ASTM F136), and Grade 4 CPTi (ASTM F67). Evaluation of alloy composition, microstructure, Vickers microhardness, and tensile properties was performed to determine compliance with the appropriate ASTM specification. For SCC testing, smooth tensile samples with a gauge length of 10 mm and a gauge diameter of 4 mm and notched samples with a notch root diameter of 4 mm (Kt=3.2) were prepared using low stress grinding procedures. Three smooth and three notched samples were tested in distilled H2O and Ringer's solution at 37°C. Testing was performed using the slow extension rate method at a stroke rate of 10−5 mm/s according to the guidelines established in ASTM G129. The ratio of the percent elongation (PER) and reduction of area (ROAR) of smooth and notched samples tested in Ringer's solution and distilled water were evaluated. The fracture surfaces of representative samples were also examined for fracture mode identification using SEM.Results showed that all alloys complied with the appropriate ASTM specification. SCC may be considered to occur in a material if the ductile properties in an aggressive media are inferior to the ductile properties in a non-aggressive media. Evaluations of the PER and ROAR ratios in smooth and notched samples for each alloy in Ringer's and distilled water showed no indication of SCC failure mechanisms. SEM examination of the fracture surfaces showed no differences in the fracture morphology regardless of the testing solution. These results were consistent with the mechanical testing data. It is therefore concluded that SCC mechanisms were not operating or contributing to the fracture of these alloys under the conditions evaluated.
Influence of Exposure Conditions on Bacterial Adhesion to Zirconium Alloys
Authors: Yamokoski EA , Buczynski BW , Stojilovic N , Seabolt JW , Bloe LM , Foster R , Zito N , Kory MM , Steiner RP , Ramsier RD 
Published: August 2005

Abstract
In this paper we combine surface analytical techniques (X-ray photoelectron spectroscopy, X-ray diffraction, infrared reflection absorption spectroscopy, optical and electron microscopy) with viable counts and statistical ANOVA methods to determine the propensity for biological adhesion on zirconium alloy surfaces. We compare the adhesion of laboratory and clinical strains of Staphylococcus aureus, Staphylococcus epidermidis, and Pseudomonas aeruginosa to Zircaloy-2 and Zircadyne-705 materials. Thermal oxidation of the alloys prior to exposure to biological species is also investigated. We present data for 72-h incubation of bacteria and alloys in both shaken and stationary environments. The results of our statistical analysis and experimental observations are relevant to the use of zirconium-based materials for biomedical applications.
Super Elastic Functional β Titanium Alloy with Low Young's Modulus for Biomedical Applications
Authors: Niinomi M , Akahori T , Hattori Y , Morikaw K , Kasuga T , Fukui H , Suzuki A , Kyo K , Niwa S 
Published: August 2005

Abstract
The low modulus β type titanium alloy, Ti-29Nb-13Ta-4.6Zr, was designed, and then the practical level ingot of the alloy was successfully fabricated by Levicast method. The mechanical and biological compatibilities, and super elastic behavior of the alloys were investigated in this study. The mechanical performance of tensile properties and fatigue strength of the alloy are equal to or greater than those of conventional biomedical Ti-6Al-4V ELI. Young's modulus of the alloy is much lower than that of Ti-6Al-4V ELI, and increases with the precipitation of α phase or ω phase in the β matrix phase. The compatibility of the alloy with bone is excellent. Low modulus of the alloy is effective to enhance the healing of bone fracture and remodeling of bone. Super elastic behavior is observed in Ti-29Nb-13Ta-4.6Zr conducted with short time solution treatment after heavy cold working. Total elastic strain in that case is around 2.8 %. The mechanism of the super elastic behavior of Ti-29Nb-13Ta-4.6Zr is still unclear.
Acoustic ‘Distributed Source’ Mixing of Smallest Fluid Volumes
Authors: Rathgeber A , Wassermeier M , Wixforth A 
Published: August 2005

Abstract
Acoustically driven mixing of small fluid volumes is reported. Using surface acoustic waves on a mixer chip and employing wave guiding effects in a substrate enables us to distribute a set of “virtual sources” for acoustic streaming over large areas. We demonstrate the applicability of our mixing technique to microarray applications, for mixing of individual wells in a micro titer plate, and other state-of-the-art hybridization assays.
Corrosion Behavior of Heat-Treated Duplex Stainless Steels in Saturated Carbon Dioxide-Chloride Solutions
Authors: Ezuber HM 
Published: August 2005

Abstract
Sweet and/or sour service environments require the use of corrosion resistant materials since conventional steels usually exhibit general corrosion, pitting attack, and stress corrosion cracking (SCC) under these conditions.
Long term performance and cost effectiveness must be considered when evaluating material selection. Duplex stainless steels (DSSs) may be considered useful materials under corrosive conditions. These materials are highly resistant to general corrosion and resistant to pitting attack. The low nickel content is an advantage from a SCC stand-point.
In this study, the pitting corrosion behavior of a lean duplex stainless steel (type Fe-15Cr-5Ni-1.9Cu) alloy as well as medium grade (type 3RE60 DSS) were evaluated in NaCl solutions saturated with CO2 (sweet environment), containing little or no thiosulfate species at 50°C. The effect of inappropriate heat treatment (e.g., formation of sigma phase in the 3RE60 alloy and sensitization in the lean grade DSS type) is also studied under such conditions.
The results revealed that these alloys are susceptible to chloride pitting corrosion with better performance for the 3RE60 alloy. The intensity of the chloride attack is remarkably increased with the addition of CO2, the presence of thiosulfate species, and with the application of inappropriate heat treatment.
Although chloride solutions containing saturated dissolved CO2 are more corrosive than those containing thiosulfate species, the presence of both species (CO2 and S2O32) has a more negative effect on the chloride pitting resistance than on each component separately. More severe attack was obtained for heat-treated samples immersed in chloride solutions containing both dissolved carbon dioxide and thiosulfate ions.
A Preliminary Mathematical Removal-Rate Model for Si CMP
Authors: Estragnat E , Martin JM , Ng D , Kulkarni M , Liang H 
Published: August 2005

Abstract
Based on the experimental removal rate data of silicon chemical-mechanical polishing (CMP), we conducted mathematical analysis on effects of surface roughness, asperities, and different length scales on material removal rate. A preliminary physical model was developed enabling consideration of mechanical and chemical removal during the Si CMP process. This model is compared with experimental results obtained through a tabletop polisher. Research results showed that the removal rate decreased with time and eventually became constant. The model has a higher prediction power when the surface roughness is high. However, with a smooth surface, the asperity height does not take a major role in the model. In such, the chemical interactions become important.