bluuebunny/crossref_metadata_2025_split huggingface dataset:
Agricultural Granule Particle Size Considerations
Authors: Goss GR 
Published: August 2005

AbstractWhen developing a granular pesticide formulation, the choice of an appropriate particle size is crucial. Particle size may or may not affect the desired performance parameters. Some of the properties to consider are sorptivity, bulk density, particle count per unit weight, hardness, drift potential, and application pattern. Depending on the nature of the carrier, particle size has little effect on bulk density and sorptivity. Particle size affects particle count per unit weight, drift potential, and possibly application pattern.
On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
Authors: Kapoor K , Padmaprabu C , Saroja S , Paul T , Rao SVR , Sanyal T , Narayan Rao M , Saibaba N , Kashyap BP 
Published: August 2005

Abstract
Two-phase alloys of zirconium, Zr-1wt% Nb and Zr-2.5wt% Nb, are widely used in nuclear reactors as fuel-clad and structural material, respectively. Post-irradiation studies on Zr-Nb alloys have shown Nb rich β (containing more than 50wt% Nb) precipitation within the α-Zr phase. In the present study, slow deformation of the two alloys at elevated temperature was carried out on unirradiated material at different temperature up to 873 K. Secondary phase (β-Nb), identified by TEM, micro diffraction and Energy Dispersive Spectroscopy, was observed to precipitate within the primary phase (α-Zr), which is similar to the observations in the irradiated material. The precipitation was dependent on temperature and imposed strain. Measurements of the lattice parameter of the α-Zr phase using X-ray diffraction show a sharp increase in samples deformed above 550 K, where the precipitation was also observed. This change is due to Nb drawn out of the supersaturated α-Zr phase during precipitation. There is a progressive increase in the dislocation density, measured by X-ray diffraction, due to strain on elevated temperature tensile deformation (up to 723 K). No such change in lattice parameter was observed in the case of samples aged at test temperatures without deformation. Dislocations generated during deformation provide enhanced Nb diffusivity, increased preferential nucleation sites, and reduced the strain energy required for nucleation of the β-Nb phase within the existing α-Zr phase. The similarity in the secondary phase precipitation observed between slow deformation at elevated temperature and irradiation is explained on the basis of dislocation-enhanced precipitation. The change in the texture due to the uniaxial tensile deformation at elevated temperature gives information on the acting deformation mechanisms. By measurement of texture at each test temperature, the deformation mechanisms were determined, which is related to the observed precipitation behavior.
Characterization and Analytical Application of the Ion-Association Complex of Nickel with Alizarin Yellow R and Eosin
Authors: Hashem EY 
Published: August 2005

Abstract
The reaction of nickel (II) with [5-(4-nitrophenylazo)salicylic acid] Alizarin yellow R (AYR) as a primary ligand and eosin as a secondary ligand was studied spectrophotometrically in the presence of Tween 80, 50 % (v/v) ethanol-water medium and an ionic strength of 0.1 M (NaClO4). The solution spectra of the mixed-ligand complex formed are characterized by high intensity (ɛ = 3.3 × 105 L mol-1cm-1) charge transfer at 575 nm. The study reveals the formation of an ion-association complex having the composition Ni: AYR: eosin (2: 1: 2), and the corresponding molecular formula is (Ni)2(AYR)(eosin)2. The optimum conditions for the spectrophotometric determination of Ni (II) have been established. A simple, sensitive, and selective method was proposed for the determination of Ni (II). The method has been applied successfully for the micro determination of Ni(II) in pharmaceutical samples. The mechanism of the reaction was also discussed.
The Performance of Different Analytical Approaches Measuring Respirable Quartz In the Workplace Analysis Scheme for Proficiency (WASP) and the Precision and Limit of Detection of the Direct On-Air-Filter Analysis Methods
Authors: Stacey PR 
Published: August 2005

Abstract
This paper describes the technique used to prepare replicate samples of respirable α-quartz on GLA5000 filters and the precision of the samples, and it compares the performance of different analytical methods for the measurement of quartz in air, used by laboratories that participate in the United Kingdom (UK) proficiency-testing program the Workplace Analysis Scheme for Proficiency (WASP). The average within laboratory relative standard deviation (RSD) of results submitted by a laboratory using an on-filter analysis method was 8.8%. The small number of laboratories using indirect methods in the program produced the most variable data (6–34 % RSD). A robust estimate of analytical precision for an 8-h sample containing 0.05 mg/m3 of quartz (53 μg on the filter) is about ± 12 % (1σ) for the direct on-filter XRD method and about ± 14 % (1σ) for the direct on-filter infrared method. The analytical precision estimates for a 4-h sample (26 μg on the filter) are likely to exceed 30 % (1.96σ). The limits of detection for the direct on-filter analysis methods are comparable with those stated in the NIOSH methods [1,2], and a comparison of the performance of X-ray diffraction and infrared analysis shows that the difference between results produced from the two techniques is insignificant for some types of dust(s).
Statistical Significance of the Restrained Slab Test for Quantifying Plastic Cracking in Fiber Reinforced Concrete
Authors: Qi C , Weiss J , Olek J 
Published: August 2005

Abstract
Fiber reinforcement has been shown to reduce the detrimental aspects of plastic shrinkage cracking in concrete. However, no standard test method currently exists to quantify the efficiency of various types or volumes of fiber reinforcement. This study was performed to evaluate the effectiveness of the restrained slab test for assessing plastic shrinkage cracking. Plastic cracking was initiated in a drying environment, and the cracks that developed in the restrained slab were analyzed using both optical microscopy and automated image analysis. The crack width data were analyzed to determine the number of measurements that are required to provide reasonable statistical significance. Statistical analysis was used to establish the variability that can be expected with this test method. The crack reduction ratio (CRR) was assessed to determine the number of replicate specimens required for a given level of statistical significance. In addition, a modified Weibull approach was used to quantify the variable nature of crack width measurements using three parameters that are related to physical features of the crack.
Cement-Admixture Interactions Related to Aluminate Control
Authors: Sandberg PJ , Roberts LR 
Published: August 2005

Abstract
Proper aluminate control has a strong effect on the performance of most portland cement based mixtures. Insufficient aluminate control typically results in poor admixture dosage efficiency, loss of workability, and in extreme cases abnormal retardation of strength development. The amount of soluble sulfate needed for proper aluminate control depends on the reactivity of the aluminate phases, not the nominal amount given by chemical analysis. Many admixtures impact both the reactivity of the cement phases, the dispersion and wetting of cement grains, and sometimes also the rate of dissolution of the sulfates. Hence, it is imperative that cement and admixture must be tested together in performance tests. This paper reviews some basic cement-admixture chemical interactions and presents some examples of the application of isothermal calorimetry as a performance test of the hydration kinetics of portland cement in the presence of admixtures.
Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
Authors: Toffolon-Masclet C , Barberis P , Brachet J-C , Mardon J-P , Legras L 
Published: August 2005

Abstract
This work is aimed at improving our knowledge of the Nb and Fe precipitation in the low α-temperature range as a function of Fe and Sn contents in ZrNb based alloys. Several experimental variants, with Nb contents ranging from 0.3–0.8 wt%, Fe from 0.01–0.5 wt% (and also Sn additions), have been studied, with special attention paid to the residual Nb content in the matrix, and to the SPP crystallographic nature and chemical composition as a function of the nominal alloy composition, annealing time/temperature, and initial metallurgical condition.
For ZrNb alloys, recent studies have pointed out the necessity of performing long term annealing treatments in order to avoid the persistence of metastable phases, and to reach a thermodynamic equilibrium state of precipitation. For that purpose, experimental alloys were annealed for up to 2 years at 400, 470, and 550°C. The evolution of SPP chemical compositions with temperature and annealing time was first quantified. For the longer annealing times, i.e., for conditions close to thermodynamic equilibrium, the results suggest an existence of a composition range for the SPP phases under equilibrium conditions. This specific point is currently taken into account to improve the thermodynamic description of the ZrNbFe phase diagram.
Also, the influence of preliminary cold work on the precipitation kinetics of equilibrium βNb phase has been investigated. This study was conducted on two Zr-1%Nb alloys containing initially metastable βZr precipitates. It was observed that cold work significantly accelerates the precipitation of equilibrium βNb phase, mainly for annealing treatments too short to allow significant recovery of the dislocation network, i.e., between 1 and 100 h of annealing.
Finally, all of these experimental results are discussed with regard to their consequences on the thermodynamic modeling of the equilibrium phase diagram and precipitation kinetics.
Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
Authors: Bocharov O , Zavodchikov S , Belov V , Kabanov A , Kotrekhov V , Rozhdestvenski V , Filippov V , Losistskiy A , Shikov A 
Published: August 2005

Abstract
A series of investigations has been performed to determine the maximum plasticity of Zr1%Nb alloy material. Also, the deformation limits for Zr1%Nb alloy material were determined. Tests in tension and compression were performed. During these tests the basic value of resistance to deformation and plasticity of the Zr-1%Nb alloy was determined under the temperature and strain rate conditions typical of hot deformation processing. The best temperature range is identified for the hot deformation processing of the Zr-1%Nb alloy. Also, a mathematical model is identified for the maximum plasticity as a function of the deformation conditions. That dependence has been used for the development of the high-tech processes for zirconium product manufacturing for nuclear application.
Improved ZIRLOTM Cladding Performance through Chemistry and Process Modifications
Authors: Yueh HK , Kesterson RL , Comstock RJ , Shah HH , Colburn DJ , Dahlback M , Hallstadius L 
Published: August 2005

AbstractSince the introduction of the ZIRLO™ alloy for use in commercial nuclear light water reactors (LWRs) in the early nineties, work has continued on identifying chemistry and process changes to improve further the in-reactor corrosion performance of the alloy. Relative to the reference ZIRLO chemistry of Zr-1%Nb-1%Sn-0.1%Fe, a series of Zr-xNb-ySn-zFe alloys was fabricated to strip material and autoclave tested. The goal was to identify Zr-Nb-Sn-Fe compositions that would result in lower uniform corrosion rates in pure water and steam environments, while retaining resistance to accelerated corrosion in abnormal chemistry conditions, such as elevated lithium levels. The results of the study identified a reduction in tin content as having the greatest impact on improving the uniform corrosion performance. However, a minimum tin content was required to avoid accelerated corrosion in water containing 70-ppm Li. In the processing area, an extensive study was conducted to evaluate the relationship between thermal-mechanical processing, alloy microstructure (e.g., second phase particles), and corrosion performance. Processing variables following β-phase heat treatments included cold work, annealing temperature, and annealing time. Long-term autoclave tests performed in 633°K water containing 70-ppm lithium showed the uniform corrosion rate of the alloy is essentially optimized in cold-worked material after only 1 h of anneal at temperatures higher than 823°K. The autoclave results also showed a lower corrosion rate with decreasing processing temperatures. A low tin version of the ZIRLO alloy, with approximately 0.75 % tin content, was fabricated into fuel cladding and inserted as fuel rods in a commercial pressurized water reactor. After two 18-month cycles at high fuel duty and average burnups greater than 52 GWD/MTU, the peak oxide thickness in the low tin ZIRLO was significantly lower than reference ZIRLO.
Development of Fuel Clad Materials for High Burn-up Operation of LWR
Authors: Cho H-S , Kimura A , Ukai S , Fujiwara M 
Published: August 2005

Abstract
Oxide dispersion strengthening (ODS) steels have been considered to be very promising for fuel clad materials for high burn-up operation of light water reactor and super critical water reactor. For improving the corrosion resistance, increasing chromium concentration, which often resulted in degradation of mechanical properties and thermal embrittlement, has been required. In this work, the effects of aluminum addition on the mechanical properties of high chromium ODS steels have been investigated. Various ODS steels which have 14 ∼ 22 wt% Cr concentrations were made by mechanical alloying method. In order to evaluate the mechanical properties and the effect of thermal aging, a miniaturized Charpy V notch test and tensile test were performed before and after aging. 1) The addition of Al resulted in the decrease in anisotropy of tensile properties, although it reduced the tensile stress. 2) The impact properties of 19Cr-ODS steel are improved by the addition of Al.
Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening
Authors: Mathon M-H , de Carlan Y , Averty X , Alamo A , de Novion C-H 
Published: August 2005

AbstractMartensitic/ferritic steels (containing 7–13 % Cr) are candidate materials for internal structures in pressurized water, fast breeder, and fusion reactors. Approval for use requires verification of structural stability under neutron irradiation in relation to the evolution of mechanical properties. In this context, several conventional and Reduced Activation (RA) martensitic materials were neutron irradiated at 325°C up to 6 dpa. They were investigated by Small Angle Neutron Scattering (SANS) under a magnetic field after various doses.It was shown that when the Cr content of the b.c.c. ferritic matrix was larger than a critical threshold value (∼ 7.2 at.% at 325°C), the ferrite separated under neutron irradiation into two isomorphous phases, Fe-rich (α) and Cr-rich (α′). The kinetics of phase separation is much faster than under thermal aging. The quantity of precipitated α′ phase increases with the Cr content and the irradiation dose. In the case of steel with the lowest Cr content (F82H) irradiated at 5.6 dpa at 325°C, the α′ phase does not form, and the SANS signal suggests a small contribution due to vacancy clusters. It was believed that these could contribute to the “black dots” observed by TEM. Furthermore, we studied the microstructural features responsible for the secondary hardening phenomenon detected in the as-quenched F82H martensitic steel during irradiation or annealing.In addition, the microstructural evolution of the Oxide Dispersion Strengthened (ODS) steel MA957, which presents an excellent hardening/ductility compromise after irradiation, has been also characterized. The stability of the oxides has been elucidated, and an important α′ volume fraction has been detected.The contribution of α′ to the irradiation-induced hardening was assessed. This, although not negligible, is not the critical factor in normalized and tempered or cold-worked steels. However, it may be the main contribution to hardening in MA957.
TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor
Authors: Abolhassani S , Restani R , Rebac T , Groeschel F , Hoffelner W , Bart G , Goll W , Aeschbach F 
Published: August 2005

AbstractMetal-oxide interfaces of three different materials irradiated in a pressurized water reactor have been analyzed by TEM and AEM. Standard Zircaloy-4, low-tin Zircaloy-4, and Zr-2.5%Nb were used for this study. The microstructure of the material on the two sides of the metal-oxide interface, the geometry of the interface, the distribution of different alloying elements, and the oxygen profile have been examined in each material. Results of the examinations showed that the three materials had different microstructure and oxygen distribution on the two sides of the metal-oxide interface. In particular, the following parameters were noticed: a) the geometry of the interface seems to be of a different nature in the case of Zr-2.5%Nb alloy. Unlike the Zircaloy-4 alloys, which show an undulated interface, this material has a “jigsaw” type interface. This point is discussed, and its role on the oxidation is considered. b) Hydrides are observed and analyzed in the vicinity of the interface in the case of low-tin Zircaloy-4, and it is shown that they can have an influence on the occurrence of cracks in this material. c) The origins of stress are discussed, and it is shown that it can have different sources. The crystal structure of the oxides is mainly monoclinic. A tetragonal oxide is observed at some regions, in particular in the standard Zircaloy-4.
Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
Authors: Pan ZL , St Lawrence S , Davies PH , Griffiths M , Sagat S 
Published: August 2005

Abstract
To determine the fracture properties of Zr-2.5Nb pressure tubes irradiated until the end of design life, cantilever beam, curved compact toughness, and transverse tensile samples were prepared from a typical pressure tube and irradiated in the high flux reactor OSIRIS at CEA, Saclay, France. Experiments were conducted on two batches of samples mounted in two irradiation inserts. Each insert held sixteen samples of each type of specimen. The first insert was irradiated to a fluence corresponding to approximately half of the design life in a CANDU3 reactor. The experimental results were reported in [1]. Samples in the second insert were irradiated for 10.5 years in OSIRIS and received a maximum neutron fluence of 2.61 × 1026 n/m2 (E &gt; 1 MeV), being equivalent to 2.98 × 1026 n/m2 (E &gt; 1 MeV) in a CANDU reactor, i.e., corresponding to ∼30 years operation in CANDU reactors at 80 % capacity factor. The present report describes the results of tensile, fracture toughness, and Delayed Hydride Cracking (DHC) tests and XRD microstructure analysis from the second batch of specimens. A continuous and gradual evolution in tensile, fracture, DHC properties, and dislocation densities is demonstrated without any evidence of a sudden change following the initial transitient at very low fluence. In the whole high fluence range, there is a very slow rate of increase in c-component dislocation density, strength, and DHC velocity and a slow reduction in elongation and Nb concentration in the β-phase. The a-type dislocation density and fracture toughness remain approximately constant. The results from the second insert of specimens confirm that, following the initial transient at very low fluence, there is little further change in the fracture properties of Zr-2.5Nb pressure tube material. Therefore, material properties behave in a stable and predicable manner to the end of a 30 years design life for CANDU reactor pressure tubes.
Performance of a New Co-Polymer Sulfonate-Based Mid-Range Water-Reducing Admixture
Authors: Saric-Coric M , Dénommé Y , Pagé M , Aïtcin P-C 
Published: August 2005

Abstract
At the present time, there are essentially two types of water-reducers: high-range water-reducers and conventional water-reducers. Superplasticizers allow a 15–30 % water reduction. They are very efficient to disperse cement particles in concretes made with W/C ratios between 0.25 and 0.45. For concrete having a W/C ratio between 0.45 and 0.60, the optimal dosage is not generally very high and lacks robustness. In industrial applications, the use of superplasticizer in 0.45–0.60 W/C ratio concrete can result in segregation (light over-dosage) or a rapid slump loss (light under-dosage).
The use of conventional water-reducers, obtained mostly from more or less processed and treated industrial by-products, results in a water reduction of between 5 and 10 %. Moreover, because they almost always contain some impurities, essentially sugars and surfactants, their dosage cannot be increased without causing excessive air entraining and a long delay in setting.
To cover the W/C ratio range between 0.45 and 0.60, it is necessary to use admixtures of the mid-range family, which are usually obtained by mixing a superplasticizer and a conventional water-reducer or a water-reducer and an accelerator. This method presents several disadvantages linked to formulation adjustment and to the availability and quality of lignosulfonate water-reducers, which may decrease in the future due to a drastic change in the production of pulp and paper worldwide.
A new type of synthetic mid-range water-reducer has been developed in order to meet the requirements of the mid-range water-reducers: comfort of rheology, no effect on setting time, and no air entrainment. It is a co-polymer of the polysulphonate family adapted for concretes made with a W/C ratio between 0.45 and 0.60. The performance of the last version of this product has been studied on grouts having a water/cement ratio of 0.45 and on concretes having a water/cement ratio of 0.44. This performance has been compared to the performance of two commercial mid-ranges and a classic water-reducer, lignosulfonate-based.
The synthetic mid-range showed a very promising dispersing performance and robustness adapted to the concrete formulation generally covered by mid-range water-reducers. Its very definite chemical composition and its controlled production make this new polysulphonate co-polymer an interesting alternative for the formulation of mid-range water-reducers.