bluuebunny/crossref_metadata_2025_split huggingface dataset:
Retention of Heavy Metals in the Post '96 Flood Sediment Layer Deposited in the Saguenay River, Quebec, Canada
Authors: Galvez-Cloutier R , Muris M , Locat J , Bourg C 
Published: April 2008

In July 1996 during a 50 year event flood, a new layer of sediments composed of debris, gravel and fine materials was transported and deposited over an ancient, one meter contaminated layer of sediments in the Saguenay River Fjord and Ha! Ha! Bay floors. During the Industrial Revolution years, various metallurgic, plastic, aluminum and pulp and paper production industries discharged their wastes on these waters, resulting in the high contamination of both water and sediments. This contamination limited the exploitation of fish and seafood. Given that the new layer is composed essentially of cleaner material, the zone is presenting important changes in the direction of a healthier environment. The Canadian Government and some of the surrounding industries aim to assess the new potential of the zone and its environmental safety. At present, it represents over a million-dollar study.
This part of the Saguenay project aimed to recognize and evaluate the capacity of the new layer to contain and retain the contaminants left at the bottom layer. Particular interest is given to mercury and to heavy metals such as Pb, Zn, Cd, and Ni and to their geochemical distribution among natural adsorbing materials such as clays, oxides, carbonates and organic matter.
The paper presents the recognition and sampling mission on the Alcide Horth Ship, the contamination profiles given in two dimensions (length and depth), the geochemical distribution of heavy metals on the contaminated layer, transition layer and new layer as well as the evolution of their retention and transfer. Discussion and relations with common sediment characteristics such as grain size, cation exchange capacity and surface area are also given. Sequential selective extraction has been used jointly with scanning electron microscopy (SEM) to study heavy metal species.
Promoted Ignition-Combustion Behavior of Cast and Wrought Engineering Alloys in Oxygen-Enriched Atmospheres
Authors: Zawierucha R , Samant AV , Million JF 
Published: April 2008

Promoted ignition-combustion has been used to describe a situation in which a substance with low oxygen compatibility ignites and supports the combustion of a more combustion-resistant material. Previous work has been reported on the investigation of this phenomenon as it relates to carbon steel, stainless steels and a number of significant engineering alloys in the nickel, cobalt and copper families.
Reported in this paper are the results of promoted ignition-combustion tests of wrought nickel alloys, cast nickel alloys and nickel alloy weld filler metals in oxygen atmospheres at pressures up to 34.5 MPa. The specific alloys tested were: CX2MW, CW2M, Hastelloy C-4, Hastelloy X, Inconel 601, Inconel 617, Inconel Welding Electrode 117, Inconel Welding Filler Metal 82 and 602CA.
The Effect of Aging on Mechanical Properties of Melt-Annealed Highly Crosslinked UHMWPE
Authors: Bhambri S , Gsell R , Kirkpatrick L , Swarts D , Blanchard CR , Crowninshield RD 
Published: April 2008

Crosslinking has been shown to improve significantly the wear resistance of ultra high molecular weight polyethylene (UHMWPE), both in joint simulator tests and in clinical use. High-energy ion radiation, when used to induce crosslinking in UHMWPE, produces free radicals. In the presence of oxygen, the free radicals have been shown to be responsible for oxidative degradation of polyethylene. A melt-anneal treatment of highly crosslinked UHMWPE substantially eliminates the free radicals to an undetectable low level.
The aim of this study was to determine the effect of accelerated oxidative aging on the mechanical and fracture properties of melt-annealed highly crosslinked UHMWPE. Compression molded GUR 1050 UHMWPE was crosslinked by electron-beam irradiation at 100 ± 10 kGy and was followed by a melt-anneal treatment. Both melt-annealed highly crosslinked and conventional gamma irradiated in nitrogen UHMWPE were exposed to an accelerated oxidative challenge in the laboratory. The tensile mechanical properties and crack growth resistance curves (J-R curves) determined for oxidative aged melt-annealed highly crosslinked UHMWPE were either equivalent or superior to the oxidative aged conventional gamma irradiated UHMWPE. The difference in tensile mechanical properties and J-R curves for non-aged and oxidative aged melt-annealed crosslinked UHMWPE was insignificant, indicating that oxidative aging had no detrimental effect on mechanical and fracture properties of melt-annealed highly crosslinked UHMWPE.
Fuel Analysis by Filter Furnace Electrothermal Atomic Absorption Spectrometry
Authors: Tittarelli P , Priola M , Ricchiuto S , Katskov DA , Ngobeni P 
Published: April 2008

The determination of Mn, Fe, Co, and Zn was performed in gasoline, jet, and diesel fuel samples by electrothermal atomic absorption spectrometry using the Transverse Heated Filter Atomizer (THFA). Thermal conditions were experimentally defined for the investigated elements.
The elements were analyzed without the addition of chemical modifiers, using organometallic standards for the calibration. Gasoline samples were analyzed directly, while jet and diesel fuel samples were diluted 1+3 with n-heptane.
The following LODs were obtained using 40 μL injections: 0.08 μg/L Mn, 0.35 μg/L Fe, 0.54 μg/L Co, and 0.06 μg/L Zn. The limits of determination, calculated for diesel and jet fuel samples, were 1.2 μg/kg Mn, 4.9 μg/kg Fe, 7.6 μg/kg Co, and 0.8 μg/kg Zn. The corresponding limits of quantitation for gasoline samples were about four times higher.
Pyro-Electrochemical On-Line Ultra Low Sulfur Analyzer
Authors: Rhodes JR 
Published: April 2008

Current and upcoming regulations worldwide require maximum concentrations of sulfur in fuels to be in the range 10–50 mg/kg. This paper describes a new on-line analyzer for ultra low sulfur, the first to employ “Pyro-electrochemical” technology, which is significantly simpler than other pyrolysis methods such as Pyro-microcoulometry and Pyro-UV fluorescence.
The technology is based on ASTM D 6920. The instrument is described with special reference to the modifications needed to adapt the technique to on-line analysis. Experimental results are given for long term stability, sensitivity, precision, speed and linearity of response, temperature stability, and sensitivity to nitrogen.
Comparison of Fracture Toughness of Irradiated Reactor Vessel Welds — Predicted by ASTM E 900 and Measured
Authors: Yoon KK , Pavinich WA 
Published: April 2008

Recently, a new predictive model has been developed by the NRC and is being implemented in ASTM Standard E 900, that addresses radiation-induced embrittlement of ferritic steels. The model is based on extensive Charpy impact energy data of irradiated reactor vessel steels obtained from surveillance programs. The final application of this new method is to predict fracture toughness of irradiated materials to determine pressure-temperature curves for nuclear power plant operation and RTPTS values in compliance with the current regulatory rules for the nuclear-utility industry.
In this paper, the predicted fracture toughness of irradiated reactor vessel welds is compared with that of irradiated material. The degree of conservatism in the Charpy impact energy based predictive model is assessed by comparison with the actual fracture toughness of irradiated materials.
Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation
Authors: Hübner R , Ehrlich K 
Published: April 2008

A pressurized tube experiment was carried out in the British Prototype Fast Reactor (PFR) at Dounreay, U.K. in order to determine swelling and stress-induced swelling of four heats of the commercial German austenitic steel DIN 1.4970, with different contents of the minor alloying elements Si, Ti and Ti/C ratio. The maximum doses achieved are 106 dpaNRT at 420°C, 81 dpaNRT at 500°C and 61 dpaNRT at 600°C. The hoop stresses of the pressurized tubes were 0, 60 and 120 MPa at all irradiation temperatures. TEM-examinations have been carried out to determine the influence of the minor alloying elements and the stress on the void swelling and the microstructural evolution. All alloys exhibited the highest swelling values at 420°C and no swelling at 600°C. The measurements show the large effect of the minor alloying elements upon swelling and in-pile creep. The maximum swelling suppression is achieved by a high Si-content and an understoichiometric Ti/C ratio (understabilization). The analysis of the microstructural evolution shows that the swelling resistance is correlated to the formation and stability of very fine γ'-precipitates. For the alloy with the highest swelling resistance these precipitates can be found up to 106 dpaNRT at 420°C, whereas they dissolve in the course of irradiation for the alloys with lower swelling resistance.
The estimates of the stress-induced swelling using the Soderberg theorem and the length measurements are compared with immersion density measurements and results of void structure analysis by TEM. All methods yield the same order of magnitude for the stress-induced linear swelling.
On the Formation of α-Ferrite in Stainless Steel Alloys
Authors: Schüle W 
Published: April 2008

Results of investigations on the microstructure of nickel-containing and of manganese-containing stainless steel alloys by means of the electrical resistivity are reported. These investigations were completed by X-ray diffractometry, by measurements of the magnetic response and of the stored energy. The investigations were performed on AMCR- and 316-type materials and on model stainless steel alloys varying slightly in the composition of the main components of the alloys and the concentrations of the additions.
The following phases were identified: α-ferrite, γ-austenite, α'-martensite, α'def.-martensite, ε-martensite, εdef.-martensite, α-Mn and σ-phase. Small amounts of α-ferrite, α-Mn and σ-phase in stainless steel alloys cause brittleness.
It was found that α-ferrite is always formed when nucleation sites, e.g. α'-martensite and dislocations, are provided, α-ferrite is readily formed by annealing at e.g. 356°C and is dissolved again after annealing for one month at the same temperature, when the nucleation sites are dissolved or recovered.
During irradiation with high energy particles α-ferrite is formed below about 600°C in AMCR- and 316-type stainless steel alloys. The amount of α-ferrite formed at 100°C is so large that many of the stainless steel specimens broke before a dose of 0.11 dpa was obtained.
These findings require a modification of the phase diagrams of stainless steel alloys.
Neutron-Induced Evolution of Mechanical Properties of 20% Cold-Worked 316 Stainless Steel as Observed in Both Miniature Tensile and TEM Shear Punch Specimens
Authors: Hamilton ML , Garner FA , Hankin GL , Faulkner RG , Toloczko MB 
Published: April 2008

Three heats of 20% cold worked 316 stainless steel were irradiated in the Materials Open Test Assembly of the Fast Flux Test Facility producing data at three or four irradiation increments to doses ranging from 12 to 88 dpa. There were five irradiation temperatures ranging from 400 to 730°C. The specimens were in two forms, standard TEM microscopy disks and miniature tensile specimens, irradiated side by side. The tensile specimens were tested at room temperature, and the TEM disks were subjected to a shear punch test, also at room temperature. Both methods yielded very similar results, showing that the mechanical properties of these steels quickly approached and then maintained saturation levels of yield strength. The saturation levels were only slightly dependent on heat identity, but were strongly dependent on irradiation temperature. Ductility decreased with increasing exposure, however.
It was shown that the tensile and shear punch data can be well-correlated with simple expressions that reflect the differences in stress state and physical constraints of the two techniques. This allows the application of the shear punch technique to situations where steep neutron flux or gamma heating gradients, insufficient irradiated material or insufficient reactor volume prevent the use of even small tensile specimens.
Effect Of Irradiation On Structural Materials In Fusion Reactors
Authors: Tavassoli F , Burlet H , Lind A , Singh BN , Tähtinen S , van Osch E 
Published: April 2008

The ITER R&D program on the structural design criteria includes the effects of irradiation on material's properties. The work has started with the design rules for stainless steels at low temperatures (&lt; 350°C) and at moderate irradiation doses (3 – 10 dpa), where degradation of ductility and toughness are of primary concern. It is now extended to copper alloys and multi-layer components, as well as to rules for high temperature properties. A similar work has also been initiated on ferritic / martensitic steels for the future Demonstration reactor, where the operating temperature range is 250–550°C and anticipated irradiation doses are well over 70 dpa.
This paper presents an overview of the above work. It details some of the recent irradiation data obtained for stainless steel type 316LN, precipitation strengthened CuCrZr alloy, oxide dispersion strengthened Cu-A125 alloy, and commercial and low activation grades of 7–10%Cr ferritic / martensitic steels. Since most of the fusion invessel components have to be fabricated using advanced manufacturing techniques, e.g. high temperature isostatic pressing (HIP) of steel/copper/beryllium layers in ITER primary modules, the paper also analyzes effects of such processes on the materials properties and design data.
Irradiation Growth of Zirconium Alloys at High Neutron Fluences
Authors: Shamardin VK , Kobylyansky GP , Kosenkov VM 
Published: April 2008

The effect of high dose irradiation on irradiation growth in zirconium commercial Zr-1%Nb, Zr-2.5%Nb, Zr-1%Nb-1.3%Sn-0.4%Fe alloys at temperatures of ∼80 and 320–360°C has been investigated.
It is shown that the irradiation growth strain in Zirconium and Zr-Nb alloys as a function of neutron fluence sharply increases at fluences higher than (2–3)×1026 m-2 (E&gt;0.1 MeV). Zr-1%Nb-1,3%Sn-0,4%Fe alloy was observed to exhibit radiation growth at high neutron fluences.
One of the methods to reduce anisotropy of properties and dimensional changes under irradiation is fast high-frequency treatment (FHF) consisting in quenching from beta-phase following quick heating with exposure.
A Case History: Refutation of Alleged Floor Maintenance Malpractice by the Application of Forensic Biomechanics
Authors: Sacher A 
Published: April 2008

This paper is based upon the author's liability expert report prepared for the defendant's attorney who represented a general maintenance contractor. The author was retained to evaluate the technical aspects and merits of the case, and to render an opinion, which would meet the criteria of the Supreme Court's “Daubert” decision.
The complaint charged that the subject (unwittnessed) slip and fall accident was the result of negligent floor maintenance in an office building where the plaintiff was employed. And more specifically, it was due to the defendant's negligent spraying of furniture polish onto a carpeted floor, the accident situs.
A brief review of the circumstances surrounding the accident is presented, followed by: (a) select portions of the plaintiffs “remarkable” (medical terminology for significant and relevant) prior and post accident medical history; (b) the more salient aspects of the plaintiff's deposition testimony and that of the defendant's maintenance supervisor; (c) an inspection of the accident site; (d) coefficient of friction measurements of the subject carpet (before and after application of the plaintiff identified furniture polish) by two independent test laboratories retained by both the defendant and plaintiff; (e) technical considerations (the biomechanics of walking mishaps, the pathophysiologic consequences of injuries and surgeries, et al); and (f) the author's opinion, to wit, that the plaintiffs detailed description of the alleged incident was exquisitely inconsistent with the biomechanics of a slip and fall accident. But instead, it is suggested that the accident was actually the result of a stumble, the sequela of the plaintiffs prior chronic locomotor deficiencies.
Elastic-Plastic Fracture Mechanics: Where Has it Been? Where is it Going?
Authors: Landes JD 
Published: April 2008

Elastic-plastic fracture mechanics (EPFM) is the name given to a body of fracture technology that includes parameters, test methods, and analysis techniques. EPFM began in the 1960s, soon after it was recognized that the linear elastic approach to fracture mechanics was too limited to cover many engineering applications. It began in response to real engineering problems and continues to develop in the same application-driven mode. The development of EPFM spans more than three decades. It involved many people and a multitude of good ideas. Some of the people have gone on to other pursuits, and many of the ideas have been set aside or discarded in the never-ending debate about which is the best approach. The development of EPFM is not complete, nor is the controversy ended. It is important to look back at the factors that influenced such a vast development of technology before trying to forge ahead.
This paper takes a look at the area of fracture mechanics called EPFM. It considers the development of a technology that involved people, places, and a seemingly inexhaustible supply of technical ideas. It considers what happened in the past, what is going on in the present, and speculates about what will happen for the future. Its purpose is to stop for a moment and consider for EPFM: Where has it been? Where is it going?
Early Stage Fatigue Damage Characterization in Aluminum Alloys and Stainless Steels with Meandering Winding Magnetometer Technology
Authors: Weiss V , Goldfine N , Natishan M 
Published: April 2008

It is shown that pre-crack and early stage fatigue damage can be characterized by a new sensor technology, the Meandering Winding Magnetometer (MWM™). This new technology consists of a conformable sensor, the MWM, and associated measurement grids that are model based.
Measurements on type 304 stainless steel indicated that damage is readily detectable at 20% of life (N/NF = 0.2) and causes a 1.5% conductivity loss. Near failure the conductivity loss in the crack-free region was approximately 4%. In 2024 aluminum the onset of detectable fatigue damage was observed at approximately 50% of total life. For the probe geometry employed, the conductivity loss in the microcrack region just prior to failure was 7%; in the macrocrack region it reached 13%.
The Significance of the Intrinsic Threshold — What Is New?
Authors: Hadrboletz A , Weiss B , Stickler R 
Published: April 2008

Numerous investigations in the past decades have shown that the fatigue threshold is influenced by several external and internal parameters. The effect of closure as one of the dominating factors indicates the existence of ΔKth,eff as a material property. Due to the fact that the determination of closure is controversial a modified closure evaluation procedure was used in this investigation.
Using selected materials (dual phase steel, particulate reinforced Al-alloy) this modified closure procedure resulted in ΔKth,eff values of reduced scatter in comparison to conventional evaluation procedures.
An alternative concept to describe threshold conditions was suggested by introducing characteristic plastic strain contours. The dislocation configuration in the vicinity of a crack tip, revealed by the electron channeling contrast imaging (ECCI) technique in the scanning electron microscope, allowed to deduce such plastic strain values in poly crystalline Cu selected as model material.
The ECCI technique was also applied to quasi two-dimensional structures (thin foils) which may be of interest in microelectronic systems. Results show that for foils of the thickness in the magnitude of the grain size a crack growth behavior is observed which appears not to be affected by closure.
Near-Threshold Fatigue Strength of a Welded Steel Bridge Detail
Authors: Albrecht P , Wright WJ 
Published: April 2008

This paper consists or three parts. First, fatigue test data are presented for a tensile specimen with transverse stiffeners, a typical steel bridge detail. The specimens were tested under variable-amplitude fatigue for up to 250,000,000 cycles of loading proportional to the gross vehicle weight distribution of 27,000 trucks weighed on highways. Few and, in some cases, no stress ranges exceeded the endurance limit in the longest life tests. It took up to nine months to test the longest-life specimens.
Second, the variable-amplitude S-N life is predicted with an equivalent stress range model in which stress ranges smaller than the fatigue limit are assumed not to contribute to fatigue damage. A simplified S-N model is proposed for determining the fatigue life of existing bridges. The variable-amplitude fatigue limit is shown, both experimentally and analytically, to be a function of the constant-amplitude fatigue limit and the ratio of root-mean-cube stress range to maximum stress range of the variable-amplitude load spectrum.
In the third part of the paper, the variable-amplitude fatigue lives of the transverse stiffener specimens are predicted with a fracture mechanics model of crack growth.
Current Structure and Activities of ASTM Committee D09
Authors: Baker DK 
Published: April 2008

Over the last 14 years, the span of my direct involvement with ASTM, many changes have occurred not only in the membership and goals of Committee D09, but also in ASTM itself. This paper will highlight the various Subcommittees within Committee D09 and some of the activities that have been completed over the past several years. In addition, the current topics of discussion within these Subcommittees will be pointed out. Committee D09 has a working relationship with other ASTM committees and standards organizations and some of these activities will be covered as well.
D09 membership is made up of approximately 160 individuals representing users, manufacturers, and general interest groups. Members may participate in as many subcommittees as they desire. In D09 the 160 members are responsible for 194 standards.
The scope of D09 is to develop test methods, practices, terminology, specifications, and promote knowledge and research relating to solid and solidifying fluid electrical insulating materials.
The principal materials included are grades designed primarily for electrical insulating or dielectric purposes of the following: • Varnishes and resins • Reinforced, laminated, filled and unfilled themoplastic and thermosetting plastics • Metal-clad dielectrics • Glass and Mica • Embedment resins, compounds, and waxes