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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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200 records · Page 12

Construction of Eu2+ doped H3Sr6(PO4)5·2H2O with novel cruciate multilayer microarchitectures: facile hydrothermal synthesis, growth mechanism, and luminescence properties

Highlights: • H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} phosphors were synthesized via a simple hydrothermal method. • H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} showed novel cruciate multilayer microarchitectures. • Phase and morphology were depended on the optimization of the reaction conditions. • H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} exhibited intense characteristic blue emission of Eu{sup 2+}. - Abstract: A series of monodisperse cruciate multilayer H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} microarchitectures assembled by crossed nanorods have been successfully synthesized via a facile surfactant-assisted hydrothermal route. XRD and FT-IR confirmed the existence of crystalline water in the phosphor. The FE-SEM images revealed that the phase and morphology of resulting samples were strongly depended on the optimization of the reaction conditions, especially the pH value and the molar ratio of citric acid (CA)/Cations. Furthermore, the possible growth mechanism of H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} microarchitectures was proposed in detail. Under near-ultraviolet excitation of 365 nm, the as-obtained H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:0.05Eu{sup 2+} sample exhibited intense wide characteristic blue emission of Eu{sup 2+}, which could be decomposed by Gaussian fitting into two peaks corresponding to different Eu{sup 2+} luminous centers. The present results demonstrated that the morphology-tunable H{sub 3}Sr{sub 6}(PO{sub 4}){sub 5}·2H{sub 2}O:Eu{sup 2+} microarchitecture could be used as a potential candidate for future optoelectronic device applications.

77 NANOSCIENCE AND NANOTECHNOLOGY↗

Microstructural characterization of cold-worked 316 stainless steel flux thimble tubes irradiated up to 100 dpa in a commercial Pressurized Water Reactor

Two flux thimble tubes (FTT) made of 15% cold-worked 316 stainless steel (SS) were harvested from Ringhals Pressurized Water Reactor (PWR) Unit 2, with peak damages of 76 and 100 displacements per atom (dpa) after 29 and 34 years’ service, respectively. Specimens sectioned from parent tubes were comprehensively characterized with nominal damage levels of ~0, ~41, ~74, 76, and 100 dpa at a nominal temperature range of 285-323 °C. Both FTTs contained helium and hydrogen gases as transmutation products. The helium follows a production rate of ~9.8 appm/dpa, while environmental factors complicate hydrogen production obscuring an exact H/dpa ratio. Irradiation-induced dislocation loops, nano-cavities, solute clusters, and microsegregation were all observed. The dislocation loops and nano-cavities indicated saturation at 41 dpa. The solute clusters continued to evolve with Ni-Si clusters formed at 41 dpa, and Ni-Si-Mn-P clusters formed at 74 and 100 dpa, but neither clusters exhibited distinct diffraction patterns at any damage levels. Solute clusters were observed to frequently be co-located with dislocation loops, but fully decorated loops were rarely detected. Significant radiation-induced segregation (RIS) was observed around grain boundaries at all damage levels. The modified inverse Kirkendall (MIK) model captured the RIS behavior of major elements. Large cavities within or around an Mn-S rich region were observed for the first time. Through all the damage levels, void swelling is always below 0.05%, making significant dimensional change unlikely in core internals when used at similar conditions. Meanwhile, the role of overwhelming nanocavities, presumably helium bubbles, should be considered in other potential degradation mechanisms, including irradiation-assisted stress corrosion cracking, embrittlement, and loss of fracture toughness, which remain the concerns for extended operation of nuclear power plants.

Post Irradiation Examination, Isotope Dilution Mas↗