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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Solution Structural Studies of Pre-amyloid Oligomer States of the Biofilm Protein Aap
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Magnetism and Mössbauer study of formation of multi-core γ - Fe 2 O 3 nanoparticles
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First principles study of the structural, electronic, and optical properties of Sn 2+ -doped ZnO–P 2 O 5 glasses [First principles study of the structural, electronic and optical properties of Sn-doped ZnO-P2O5 glasses]
The atomic-structural, electronic, and optical properties of Sn-doped ZnO–P 2 O 5 glasses are examined using combined semi-empirical and density functional theory calculations. From model structures for two different ZnO–P 2 O 5 glass compositions, it is found that these glasses consist of nearly ideal tetrahedral PO 4 unit and largely distorted ZnO 4 and ZnO 5 units. The concentration of ZnO 5 units is calculated to increase and exceed that of ZnO 4 as the amount of ZnO in the glass is increased. Also, the concentration of terminal oxygen atoms shared by two Zn neighbors is largely increased for 70ZnO:30P 2 O 5 (70:30) glass compared to 60:40 glass, which can be rationalized by electrostatic bond strength calculations. Regarding medium-range order, calculations show that Q 1 and Q 2 structures (where Q n refers to structures containing n bridging oxygen atoms on PO 4 tetrahedra) are dominant for the 60:40 glass, while Q 0 and Q 1 prevail for the 70:30 glass, in good agreement with experimental observations. For the Sn-doped ZnO–P 2 O 5 glass, various Sn coordination geometries are found, with trigonal pyramidal SnO 3 and largely distorted pyramidal SnO 4 configurations being dominant and a small fraction of two-fold and five-fold coordinated Sn configurations also present. From combined cluster and glass model calculations, two-fold coordinated Sn are found to exhibit slightly smaller optical transition energy than three-fold and four-fold coordinated Sn. However, local variations in coordination structures throughout the glass likely result in a broad singlet transition (S 0 →S 1 ) around 5.4 eV for all the different Sn configurations. Finally, a triplet transition (S 0 →T 1 ) driven by spin-orbit coupling can occur around 4.5 – 4.8 eV, but the magnitude of this transition is predicted to be much smaller than the spin-allowed singlet transition.
Role of short range order on crystallization of tectosilicate glasses: A diffraction study
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Atomistic study of grain boundary sink strength under prolonged electron irradiation
Grain boundaries (GBs) are sinks and sources of point defects, which are produced in large number under radiation damage. As grain size decreases, many of the point defects sink into GBs. It is unknown whether GBs will saturate as sinks of point defects, particularly when grain size is at the nanoscale. Using a combination of molecular dynamics (MD) simulations and rate theory for BCC Mo, the authors show that large-angle GBs do not saturate as sinks of point defects. The MD simulations serve to provide direct measurement of defect evolution, and the rate theory serves to test whether grain boundary sink strength is a constant and to extend the MD results to realistic defect production rates.
Cold crucible induction melter studies for making glass ceramic waste forms: A feasibility assessment
Glass ceramics are being developed to immobilize fission products, separated from used nuclear fuel by aqueous reprocessing, into a stable waste form suitable for disposal in a geological repository. This work documents the glass ceramic formulation at bench scale and for a scaled melter test performed in a pilot-scale (approximately 1/4 scale) cold crucible induction melter (CCIM). Melt viscosity, electrical conductivity, and crystallization behavior upon cooling were measured on a small set of compositions to select a formulation for melter testing. Property measurements also identified a temperature range for melter operation and cooling profiles necessary to crystallize the targeted phases in the waste form. Bench scale and melter run results successfully demonstrate the processability of the glass ceramic using the CCIM melter technology.
In situ TEM study of G-phase precipitates under heavy ion irradiation in CF8 cast austenitic stainless steel
Thermally-aged cast austenitic stainless steels (CASS) CF8 was irradiated with 1 MeV Kr ions at 300, 350 and 400°C to 1.88x10^15 ions/cm2 (~3 dpa) at the IVEM-Tandem Facility at the Argonne National Laboratory. Before irradiation, the distribution of G-phase precipitates in the ferrite showed strong spatial variations, and both their size and density were affected by the ferrite-austenite phase boundary and presence of M23C6 carbides. Under 300°C irradiation, in-situ TEM observation showed G-phase precipitates were relatively unchanged in the vicinity of the phase boundary M23C6 carbides, while the density of G-phase precipitates increased with increasing dose within the ferrite matrix. Coarsening of G-phase precipitates was observed in the vicinity of phase boundary M23C6 carbides at 350°C and 400°C.
Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe
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In-air and pressurized water reactor environment fatigue experiments of 316 stainless steel to study the effect of environment on cyclic hardening
Argonne National Laboratory (ANL), under the sponsorship of Department of Energy’s Light Water Reactor Sustainability (LWRS) program, is trying to develop a mechanistic approach for more accurate life estimation of LWR components. In this context, ANL has conducted many fatigue experiments under different test and environment conditions on type 316 stainless steel (316SS) material which is widely used in the US reactors. Contrary to the conventional S~N curve based empirical fatigue life estimation approach, the aim of the present DOE sponsored work is to develop an understanding of the material ageing issues more mechanistically (e.g. time dependent hardening and softening) under different test and environmental conditions. Better mechanistic understanding will help develop computer-based advanced modeling tools to better extrapolate stress-strain evolution of reactor components under multi-axial stress states and hence help predict their fatigue life more accurately. In this paper (part-I) the fatigue experiments under different test and environment conditions and related stress-strain results for 316 SS are discussed. In a second paper (part-II) the related evolutionary cyclic plasticity material modeling techniques and results are discussed.
High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel
Samples harvested from an HT-9 fuel test assembly (ACO-3) irradiated for six years in the Fast Flux Test Facility (FFTF) reaching 2–147 dpa at 382–504°C were deformed in-situ while collecting high-energy X-ray diffraction data to monitor microstructure evolution. With the initiation of plastic deformation, all samples exhibited a clear load transfer from the ferrite matrix to carbide particulate. This behavior was confirmed by modeling of the control material. The evolution of dislocation density in the material as a result of deformation was characterized through full pattern line profile analysis. The dislocation densities increased substantially after deformation, the level of dislocation evolution observed was highly dependent upon the irradiation temperature of the sample. The differences in both the yield and hardening behavior between samples irradiated at higher and lower temperatures suggest the existence of a transition in tensile behavior at an irradiation temperature near 420°C dividing regions of distinct damage effects.