bluuebunny/crossref_metadata_2025_split huggingface dataset:
The Effect of Substructure on the Biaxial Strength and Irradiation Stability of ASTM A 302 Grade B Steel
Authors: Flynn P. W. , Trozera T. A. 
Published: September 2009

ASTM Specification A 302 Grade B steel was given thermal-mechanical treatments to improve mechanical properties through development of substructure. Cold work of 0.06 followed by a 435 C heat treatment produced a 28,000 psi (35 percent) increase in lower yield strength without loss of uniform elongation. Specimens were irradiated at &lt;100 C and 288 C to fast fluences in the range of 1 × 1018 to 5.2 × 1019 n/cnr. Standard tension tests, biaxial stress (tube) tests, and instrumented Charpy-V impact tests were performed.
Data from the biaxial tests were analyzed on the basis of uniform strain predicted from the uniaxial (simple tension) test. A mathematical analysis of the instability criteria is included. Data from the Charpy tests were analyzed to determine (1) the relation between substructure and irradiation response in terms of the nil ductility transition temperature shift and (2) the way in which the sample breaking energy is distributed between crack initiation and propagation. Major conclusions from these analyses are: The predicted instability strain in the biaxial test is not exceeded. A constant cell size (and degree of substructure) is reached at small amounts of cold work and does not appear to be exceeded. An appropriate substructure treatment may decrease radiation sensitivity and may increase energy absorption in fracture propagation in the Charpy test.
Effects of Interstitial Elements on Radiation Hardening in Mild Steels
Authors: Little E. A. , Harries D. R. 
Published: September 2009

Neutron irradiation produces greater increases in room-temperature tensile lower yield stress of annealed silicon killed mild steel than in that of annealed aluminum grain size controlled steel. This difference in behavior is due primarily to the presence of free nitrogen in the silicon-killed steel. Preliminary results suggest that free carbon in the steels does not enhance the radiation hardening.
The amount of nitrogen in solution in the silicon killed mild steel is progressively reduced with increasing neutron dose. Furthermore, the nitrogen returns to solution and the radiation hardening is recovered on annealing at temperatures in the range 300 to 400 C.
These effects are attributed to the nitrogen and the irradiation-induced point defects forming complexes that restrict dislocation movement and thereby increase the radiation hardening.
Neutron irradiation has a marked effect on the dynamic strain ageing behavior and the temperature dependence of the yield and flow stresses of the annealed silicon killed mild steel in the range 90 to 250 C. The results are explained on the basis of a strain rate effect, assuming that channeling is the operative deformation mechanism in the irradiated steel, and thermal activation of the radiation damage.
Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel
Authors: Wechsler M. S. , Berggreen R. G. , Hinkle N. E. , Stelzman W. J. 
Published: September 2009

The relationship between the increase in tensile yield stress (YS) and the increase in the ductile-brittle transition temperature (DBTT) upon irradiation was studied for ASTM A 212-65 Grade B pressure vessel steel. Smooth tension specimens and Charpy V-notch impact specimens were irradiated in the same facility of the Oak Ridge Research Reactor under the same conditions of 60 C irradiation temperature and 1 × 1010 neutrons/cm2 (E &gt; 1 MeV) fluence. The tension tests were carried out at temperatures from 20 to 473 K at two strain rates. The YS increased rapidly with decreasing test temperature, but the radiation-produced increment in YS was largely independent of test temperature. The impact specimens also were tested as a function of temperature and the increase in DBTT was determined based on absorbed energy and fracture appearance. To correlate the changes in YS and DBTT upon irradiation, strain-rate and triaxiality corrections were applied to the tensile yield stresses to approximate the corresponding stresses at the root of the notch of the impact specimens. The results of the tension and impact tests were found to be consistent, based on a critical cleavage stress deduced from the tension tests. No evidence for a decrease in the critical cleavage stress upon irradiation was noted.
The conclusion is that the radiation embrittlement is largely a consequence of radiation hardening and not a change in fracture properties as such.
Development of a Titanium-Modified Hastelloy N with Improved Resistance to Radiation Damage
Authors: McCoy H. E. , Weir J. R. 
Published: September 2009

Our studies of the effects of neutron irradiation on the hightemperature mechanical properties of Hastelloy N have shown generally that the creep-rupture life and ductility are reduced. The ductility is a strong function of the strain rate and shows a minimum at a minimum creep rate of about 0.1 percent per hour.
The resistance of this material to radiation damage can be enhanced greatly by adding titanium. Laboratory and commercial melts have shown that the postirradiation creep-rupture ductility and strength rise sharply as the titanium content is increased above 0.3 weight percent. Although the degree of improvement is still rising as the titanium level is increased to 1 percent, most of our studies have been carried out on an alloy with about 0.5 weight percent titanium. Postirradiation creep-rupture tests at 650 C on specimens irradiated to a thermal fluence of 5 X 1020 neutrons cm2 indicate that a ductility minimum still exists as a function of strain rate. However, the minimum strain is 3 to 5 percent as compared with 0.5 percent for the standard alloy. In-reactor creep-rupture tests have also been run and the same improved properties are indicated.
Our studies of the titanium-modified alloy have not progressed sufficiently to pinpoint the exact role of titanium in bringing about the improved properties. However, several observations have been made which allow us to make some postulations at this time.
Multiaxial In-Reactor Stress-Rupture Strength of Stainless Steels and a Nickel Alloy
Authors: Laue H. J. , Böhm H. , Hauck H. 
Published: September 2009

In the framework of the cladding program for fast breeders we have tested the behavior of tubes under constant pressure during irradiation. The test facility and the type of specimens are described briefly.
The maximum available helium pressure was 500 atm and the test temperature between 600 and 700 C. Tests were run with the stainless steels, 16Cr-13Ni, 20Cr-25Ni, and Incoloy 800, and a nickel alloy, Inconel 625. The irradiation was done in the BR2 reactor at Mol, Belgium, with a fast neutron flux of 2 to 4 × 1014 n/cm2 s and a maximum time-to-rupture of 3000 h. Identical tests were done without irradiation, and the results were as follows: 16Cr-13Ni—The decrease of the stress-rupture strength under irradiation was in the range of 40 to 50 percent and the absolute tangential strain between 0.4 and 1.0 percent. Inconel 625—The comparison of different types of unirradiated specimens showed the influence of the specimen dimensions and test conditions. The stress-rupture strength of irradiated tubes was decreased by 30 to 40 percent; the corresponding tangential strain was smaller than 1 percent. Incoloy 800—The outstanding result of this alloy was the relatively high tangential strain under irradiation (3.0 to 4.5 percent). The reduction of stress-rupture strength by irradiation was of the same order as for the stainless steel. 20Cr-25Ni—The reduction of strength upon irradiation was in the range of 30 percent, and the tangential strain was smaller than 1 percent. The rupture time at a load of 9.5 kg/mm 2 at 600 C was only 2500 h.
The metallographic tests of all the irradiated specimens have shown in each case small intergranular cracks and no burst. The results are discussed and conclusions are reached concerning the optimal fuel-element design.
Some Technical Aspects of the Motor Oils Market in France and in Europe
Authors: Thiery J. 
Published: September 2009

This paper evaluates the requirements of crankcase lubricants for France and Europe by reviewing current automotive practices.
The present status of motor oil consumption for both gasoline and diesel engines is examined for France and other European countries, and future developments of engine oils are discussed.
The specific requirements for diesel and gasoline engines currently produced in Europe are listed. In this field there are some marked differences from corresponding U.S. engines and these are reviewed.
The user's situation as regards the lubricating requirements of automcbiles now being operated in France and Western Europe are discussed, and the extent to which the producers of lubricating oil can satisfy these needs is reviewed.
The paper presents a forecast on engines and lubricant developments, and the possible impact of the Common Market.
In-Reactor Creep of Zirconium-Alloy Tubes and Its Correlation with Uniaxial Data
Authors: Ibrahim E. F. 
Published: September 2009

A creep experiment on 23-mm diameter tubular specimens of Zircaloy-2 is described. The specimens are stressed biaxially at hoop stresses from 11 to 26 kgf/mm2 at 260 C at three neutron flux conditions. The results confirm that fast neutrons increase creep rates at all the stresses tested, but thermal neutrons have no detectable effect. The creep data are consistent with those obtained on larger tubes.
A method is described for correlating biaxial tubular and uniaxial in-reactor creep results for zirconium alloys and this is applied to cold-worked Zircaloy-2, cold-worked 2.5Nb zirconium, and heat-treated 2.5Nb zirconium alloys.
Texture Changes Produced During Zircaloy-4 Tubing Fabrication: From Forged Billet to Finished Tubing
Authors: Hobson D. O. 
Published: September 2009

Certain fabrication procedures yield tubing with large variations in texture around the circumference. Such variations lead to non-uniform mechanical properties and to difficulties in design specifications. The purpose of this work was to follow the texture changes that occur during fabrication from forged billet through extrusion, rocking, and straightening to finished tubing and to determine the effects various fabrication schedules have on the textures of the tubing.
We observed the development of texture inhomogeneities at each step of tubing fabrication.
The significance of this work is that, for the first time, a detailed texture study has been made through an entire set of tubing-fabrication runs under controlled conditions of starting stock, tubing reductions, and heat treatment. Such an examination yields valuable insight into the causes of varying texture quality in tubing.
Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys
Authors: Johnson A. B. 
Published: September 2009

A series of in-reactor corrosion tests was conducted in the G-7 loop of the Engineering Test Reactor (ETR) in pH 10 NH4OH at 270 to 280 C. Six zirconium alloys were exposed in as-etched and prefilmed (400 C steam) surface conditions. The six alloys were Zircaloy-2, Zircaloy-4, Zr-3Nb-1Sn, Zr-2.5Nb, Zr-1.2Cu-0.28Fe, and Zr-1.2Cr-0.08Fe. Exposures were 25, 37, 77, and 174 days in high-flux, low-flux, out-of-flux, and out-of-reactor environments. Results from the 174-day exposure are emphasized, but corrosion and hydriding data from the complete test series are compared.
A marked upturn in corrosion rate between the 77- and 174-day exposures is attributed to an increase in oxygen level near the end of a deoxygenating resin life. In the 174-day experiment, corrosion rates were accelerated on the six alloys at the high-flux position, but only on Zr-Cr-Fe specimens at the low-flux position. Prefilming adversely affected the corrosion of Zr-Cr-Fe, Zr-Cu-Fe, Zircaloy-2, and Zircaloy-4 specimens. The alloys containing niobium were the most resistant to in-flux corrosion and hybriding. Hydrogen-absorption rates were generally proportional to corrosion rates.
Monoclinic zirconium oxide was the principal phase on high-fluence (1.7 × 1021, n/cm2, &gt; 1 MeV) specimens of the six alloys. Non-uniform oxidation was observed on Zr-Cr-Fe and Zr-2.5Nb alloys, including pustules, pitting, and cracks. Banded chromium segregation was observed in a Zr-Cr-Fe oxide and nodular copper segregation was observed in a Zr-Cu-Fe oxide; niobium distribution was relatively uniform in a Zr-2.5Nb specimen.
Powder versus Slurry Application of Lime for Soil Stabilization
Authors: Davidson D. T. , G. Noguera , Sheeler J. B. 
Published: September 2009

The use of lime in soil stabilization is rapidly gaining acceptance. Both hydrated and quicklime have proved successful. Quicklime is less expensive and more effective, but hydrated lime is easier and safer to handle in the powdered state. A possible answer to the safer use of quicklime as a soil stabilizer lies in its application in the form of a slurry.
In this paper the effectiveness of limes in slurry form when applied to silty and to clayey soils is evaluated and the results are compared with stabilization by the use of limes in powdered form.
Slurries of lime were found to be easily applied and produced unconfined compressive strengths equivalent to strengths obtained through the use of powdered lime. Quicklimes in slurries produced higher strengths than those used in powdered form. Hydrated limes—powdered or in slurries—gave about equivalent strengths. The dolomitic limes were superior to the calcitic limes. The amounts of either type of lime required for near maximum 7- and 28-day strengths were found to be economical.
Shear and Torsion Testing of Wood, Plywood, and Sandwich Constructions at the U. S. Forest Products Laboratory
Authors: Youngquist W. G. , Kuenzi E. W. 
Published: September 2009

The U.S. Forest Products Laboratory has maintained a continuing interest in the development of satisfactory test methods for determining shear characteristics of wood, plywood, adhesives, and more recently sandwich constructions. The anisotropic structure of wood has added to the difficulty of developing test methods that reliably evaluate the desired properties.
This paper presents a brief description of the test methods used, traces the history of some of the methods, and presents a discussion of their advantages, disadvantages, and suitability.
Discussed are the shear and torsion tests for solid wood; the plate shear, panel shear, “rolling” shear, and tubular torsion tests for plywood; the plywood glue shear, wood glue joint shear, metal lap joint and torsion test of adhesives for metals; and the shear tests for sandwich constructions and cores. An analysis of the stress conditions in the test specimens is presented for some of the tests.
Interlaboratory Comparison of the Potential Heat Test Method
Authors: Gross D , Natrella M G 
Published: September 2009

Quantitative measurements of the total heat release by selected building materials were made during an interlaboratory study of the Potential Heat Method. Seven of the eleven participating laboratories ranked the five materials in the same order, and a single ranking change for three other laboratories would yield identical rankings. The general magnitude of within-laboratory repeatability and between-laboratory reproducibility for composite materials of generally low potential heat are indicated by statistical analysis of the results.
Results are reported on the effect of the amount of combustion promoter used and on differences in the first and second phase values. A discussion is presented on the effects of material sampling and on certain features of the experimental procedure which require special care. A tentative test method standard, containing complete details of the test procedure, is included as an appendix.
Important residue (G46) in erythroid spectrin tetramer formation
Authors: Kang Jianxia , Song Yuanli , Sevinc Akin , Fung Leslie 
Published: September 2009

AbstractSpectrin tetramerization is important for the erythrocyte to maintain its unique shape, elasticity and deformability. We used recombinant model proteins to show the importance of one residue (G46) in the erythroid α-spectrin junction region that affects spectrin tetramer formation. The G46 residue in the erythroid spectrin N-terminal junction region is the only residue that differs from that in non-erythroid spectrin. The corresponding residue is R37. We believe that this difference may be, at least in part, responsible for the 15-fold difference in the equilibrium constants of erythroid and non-erythroid tetramer formation. In this study, we replaced the Gly residue with Ala, Arg or Glu residues in an erythroid α-spectrin model protein to give G46A, G46R or G46E, respectively. We found that their association affinities with a β-spectrin model protein were quite different from each other. G46R exhibited a 10-fold increase and G46E exhibited a 16-fold decrease, whereas G46A showed little difference, when compared with the wild type. The thermal and urea denaturation experiments showed insignificant structural change in G46R. Thus, the differences in affinity were due to differences in local, specific interactions, rather than conformational differences in these variants. An intra-helical salt bridge in G46R may stabilize the partial domain single helix in α-spectrin, Helix C’, to allow a more stable helical bundling in the αβ complex in spectrin tetramers. These results not only showed the importance of residue G46 in erythroid α-spectrin, but also provided insights toward the differences in association affinity between erythroid and non-erythroid spectrin to form spectrin tetramers.
Hydrogeologic assessment and groundwater reserve evaluation in northwestern parts of Dun valley aquifers of Chitwan, inner Terai
Authors: Neupane Rajendra , Shrestha Suresh Das 
Published: September 2009

The Chitwan Valley is one of the largest Dun Valleys in the Himalayan foothills of Nepal. Dun gravels perhaps deposited in the late Pleistocene to very early Holocene about 22,000-7000 yr. B.P. Chitwan Dun Valley is underlain by Dun fan gravels or Dun gravels which form unconfined to semiconfined or leaky confined aquifers. The study area, situated in the NW part of the valley occupies an area of 70.8 km2.The hydrogeological situation in the study area is inferred from drilling data of Ground Water Resources Development Board (GWRDB), Agriculture Development Project Janakpur (ADPJ) and several private drilling companies .The Chitwan Dun Valley constitutes a closed groundwater system in the Siwalik Zone of Nepal Himalaya. The study area reveals the existence of two definite groundwater sub-basin each having its own hydraulic system and is a part of single large regional groundwater basin. Annual potential evapotranspiration (PET) calculated at Rampur (station no 0902) for five-year period (1990-1995) is 1.68 mm/day. Annual precipitation data recorded at Rampur is 2214 mm. Area of recharge is 70.8 km2 and estimation of total groundwater storage(reserve) is 87.31 MCM per year, and dynamic reserve or annual potential recharge is estimated as 48.60 MCM per year. doi: 10.3126/bdg.v12i0.2249 Bulletin of the Department of Geology, Vol. 12, 2009, pp. 43-54
Mutagenesis
Authors: Lynch Anthony 
Published: September 2009

AbstractThere is overwhelming evidence that inherited mutational changes in humans are responsible for a significant proportion of genetically determined diseases and congenital (heritable) malformations. In addition, the accumulation of somatic cell mutations is known to be implicated in cancer, and to some extent in other multifactorial diseases, for example heart disease. Thus the integrity of human DNA is essential for the future of the species and the health of its individuals. DNA damage may be induced by errors in DNA replication/repair, exposure to endogenous mutagens (such as reactive oxygen species) or by environmental factors. Novel chemicals/consumer products/drugs represent an additional potential source of damage to DNA, and so appropriate testing is required to minimise the risk of genotoxicity. The discipline of genetic toxicology as applied to chemicals/consumer product/drug development exists to achieve this aim. An additional role of genetic toxicology is the assessment of the relative risk arising from exposure to carcinogens, particularly those which are DNA reactive. The aims of this chapter are to provide an overview of the organization of the genetic material, DNA, and describe the mechanisms by which mutations arise in DNA (mutagenicity) and the links between mutations and the role they play in hereditary diseases and cancer; and also other multifactorial diseases and ageing. The chapter goes on to describe the discipline of genetic toxicology, its history and the development of assays for the measurement of mutations in model organisms. It culminates in a description of the standard regulatory battery ofin vitroandin vivotests used to assess the potential genotoxic liability of a novel test agent, plus additional supplementary tests that can be used to investigate further the underlying biological mechanisms resulting in genotoxicity. The chapter continues with a discussion on data interpretation and current concepts of risk assessment in genetic toxicology, and concludes with an outline of the challenges faced by genetic toxicology in the new millennium, and describes developments within the discipline to meet these challenges.
Simplification and application of single fiber fragmentation test on silylated polyester–glass fiber composites
Authors: Taslica Banu , Kusefoglu Selim 
Published: September 2009

AbstractSingle fiber fragmentation test (SFFT) was used to investigate the interfacial adhesion in glass fiber‐unsaturated polyester composites. A simplified approach was developed for SFFT based on determination of the maximum number of fragments on the fiber at the end of the test. This approach does not involve length measurements and shortens the experiment time to a few minutes. By using a digital camera attached to the microscope, photographs of the coupon were taken during the test, and the number of fragments within the gauge length were counted later. This method allows quick, quantitative comparison of different fibers and matrices. The test samples were prepared by using commercial polyester resin and E‐glass fibers having different commercial sizings. SFFT results were in excellent agreement with the macromechanical test done on samples prepared with the same glass fiber and same polyester. The crack modes and debonding phenomena were examined from the microscopic images. Atomic force microscopic (AFM) images of the fiber were examined to get detailed topographic information about fiber surfaces. To improve interfacial adhesion, commercial unsaturated polyester was reacted with 3‐aminopropyltriethoxy silane via Michael Addition reaction on the maleate double bonds of the polyester. The resulting silylated polyester was characterized by H1 NMR spectroscopy. The results of SFFT showed that the maximum numbers of fragments increased 23% on using silylated polyester. © 2009 Wiley Periodicals, Inc. J Appl Polym Sci, 2010
Perineal groove: A rare congenital abnormality of failure of fusion of the perineal raphe and discussion of its embryological origin
Authors: Sekaran Prabhu , Shawis Rang 
Published: September 2009

AbstractWe present a case where a baby girl was born with failure of fusion of the perineal raphe. To our knowledge, there has been limited reports of this form of congenital abnormality in the literature and is referred to as “perineal groove.” The incidence of perineal groove is unclear but it is considered to be rare. This case reviews the embryological origin of this congenital abnormality. Clin. Anat. 22:823–825, 2009.© 2009 Wiley‐Liss, Inc.