Engineering Papers⌕ Search

Engineering topics

Yang, Ying

Publications and source records attributed to Yang, Ying.

At least 109 records · Page 6
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Three-dimensional MoO3 nanoflowers assembled with nanosheets for rhodamine B degradation under visible light

Highlights: • The orthorhombic three-dimensional MoO{sub 3} nanoflowers were synthesized by the modified hydrothermal method. • Using different amount of HCl to transfer from the h-MoO{sub 3} to the α-MoO{sub 3} was well discussed. • Better pore sizes and surface areas of the three-dimensional MoO{sub 3} nanoflowers accelerate the photodegradation process of RhB. • The three-dimensional MoO{sub 3} nanoflowers showed the photocatalytic activity (91.57%). • This methodology should be useful for preparing other nanostructured catalysts. - Abstract: Three-dimensional hierarchical nanoflowers self-assembled with the orthorhombic molybdenum oxide (α-MoO{sub 3}) nanoflowers were synthesized by the modified hydrothermal method. The structure characterizations of the three-dimensional α-MoO{sub 3} nanoflowers were carried out by scanning electron microscope (SEM), Energy Disperse Spectroscopy (EDS), X-ray diffraction (XRD) and nitrogen adsorption-desorption measurement. Moreover, the three-dimensional α-MoO{sub 3} nanoflowers as photocatalyst exhibited enhanced photocatalytic activity towards photodegradation of Rhodamine B (RhB) under xenon (Xe) lamp irradiation. The results of SEM, EDS, XRD and nitrogen adsorption-desorption measurement showed the three-dimensional α-MoO{sub 3} nanoflowers have a better morphology, pore size (7.99 nm) and surface areas (50.788 m{sup 2} g{sup −1}) than hexagonal MoO{sub 3} (h-MoO{sub 3}) nanosheets, photocatalytic activity studies confirmed that the three-dimensional α-MoO{sub 3} nanoflowers photocatalyst exhibits a high visible-light-driven activity for photodegradation of RhB solution of 91.57% within 160 min under Xe lamp irradiation. A mechanism was also proposed for the degradation of RhB by three-dimensional α-MoO{sub 3} nanoflowers.

77 NANOSCIENCE AND NANOTECHNOLOGY↗
DOE OSTI2018

A novel role for Bcl2l13 in promoting beige adipocyte biogenesis

Highlights: • Bcl2l13 expression is induced in Browning of white adipose tissues in Mice. • Knockdown of Bcl2l13 in beige adipocytes represses adipogenesis and thermogenic programing. • Bcl2l13 induces thermogenic programing by regulating mitochondrial dynamic and biogenesis. Bcl2l13 is a member of the Bcl-2 family that has been found to play a central role in regulating apoptosis. Recently Bcl2l13 has been reported to induce mitophagy as a functional mammalian homolog of Atg32. However, the role of Bcl2l13 in adipose tissue has not been investigated yet. In the present study, we found that Bcl2l13 expression was increased in white adipose tissue browning process stimulated by cold exposure or β3-adrenergic agonist CL-316,243 in vivo as well as during brown adipocytes differentiation in vitro. Moreover, Bcl2l13 disruption dramatically inhibited the browning program of preadipocytes, evidenced by reduced Prdm16, Ucp1, Dio2 and Adrb3 expression. Our findings revealed that the inhibition effect of Bcl2l13 disruption on browning program may be independent of altering autophagy activity, but through regulating mitochondrial dynamic and biogenesis, supported by decreased mitochondrial fission/fussion genes, PGC-1α and mitochondrial respiratory chain complexes expression. Taken together, our study uncovered a novel function of Bcl2l13 in adipocytes differentiation and promoting browning program.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2018

Support-induced morphology and content tailored NiCo 2 O 4 nanostructures on temperature-dependent carbon nanofibers with enhanced pseudocapacitive performance

Direct anchorage of metal oxides on carbon nanofibers is challenging, and simultaneous modulation of morphology, content and thus pseudocapacitance of anchored metal oxides has never been achieved. In this paper, we report direct anchorage of NiCo 2 O 4 nanostructures with tailored morphology, content and pseudocapacitance, on temperature-dependent carbon nanofibers (CNEs), which are derived from zinctrimesic acid fibers at a temperature no more than 600 degrees C. The temperature-dependent CNEs, including CNF-390, CNF-450 and CNF-600, were first investigated by SEM, TG, FT-IR, XPS and Boehm titration studies. It is found that their textural property, thermal stability and surface functionality vary depending on pyrolysis temperature. As a result, the morphology, content and thus the pseudocapacitance of anchored NiCo 2 O 4 nanostructures are also temperature-dependent. It is revealed that as increasing the pyrolysis temperature, the shape of NiCo 2 O 4 is transformed from embedded nanoparticles to exposed nanosheets while its content decreases from 95 to 55 wt%. The resultant NiCo 2 O 4 /CNF-450, bearing highly dispersed nanosheets and optimized NiCo 2 O 4 content (72.6%), exhibits the best capacitive performance with a large specific capacitance of 870 F g -1 at a scan rate of 1 mV s -1 , and a high energy density of 39.3 Wh kg -1 in the case of power density of 300 W kg -1 . The elaborately fabricated NiCo 2 O 4 /CNF-450 also shows excellent charge-discharge stability (with the capacity retention ratio of 85.7% after 5000 cycles). The improved accessibility for more pseudocapacitive NiCo 2 O 4 nanosheets, as well as the strong interaction between NiCo2O4 and carbon nanofiber, should be responsible for the enhanced capacitive performance of NiCo 2 O 4 /CNF-450. Lastly, this research also provides the concept of support-induced modulation of property and pseudocapacitive performance of anchored metal oxides.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Development of novel Cu-Cr-Nb-Zr alloys with the aid of computational thermodynamics

Multi-modal precipitate distribution in the microstructure, with coarse precipitates pinning the grain boundaries and finer precipitates strengthening the matrix, is beneficial to suppress grain boundary sliding and dislocation creep, respectively, of structural materials. However, achievement of a multi-modal precipitate distribution remains a challenge in developing creep-resistant advanced Cu alloys while retaining high strength and high conductivity at elevated temperature. This work overcame this challenge with the aid of computational thermodynamics. Thermodynamic models for Gibbs energy functions of phases in the Cu-Cr-Nb-Zr system have been developed in this study. These models were then used to calculate solidification paths and phase equilibria at different temperatures, guiding the design of chemical composition and heat treatment parameters of novel copper alloys with a target multi-modal distribution of precipitates. The new alloy, fabricated through traditional ingot metallurgy method, has achieved the desired microstructure as validated by optical and transmission electron microscopy. Electrical conductivity and mechanical properties were screened and compared with the existing commercial Cu alloys.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Probing long-range ordering in nickel-base alloys with proton irradiation

In this paper, twelve commercial-grade austenitic alloys based on the Ni-Cr-Mo-Fe quaternary system were irradiated using 2 MeV protons at 360 °C to a damage level of 2.5 displacements per atom (dpa). Long-range ordered (Pt 2 Mo-type) precipitation under proton irradiation was observed, for the first time, in alloys C22, 625, 625P, 625D, 725, and 690. No relevant short-range ordering was observed. These irradiation-enhanced long-range ordered precipitates are coherent with the matrix despite their irregular shape. Of the potential influences on long-range ordering (Ni:Cr, and Ni:(Cr + Mo) ratios, Mo, and iron concentration), Fe content was the strongest by far. The volume fraction of LRO decreases with increasing Fe content by virtue of its role as a stabilizer of the disordered FCC phase, thus reducing the energy savings from ordering. The observed effects of Fe on long-range ordering show qualitative agreement with predictions from thermodynamic modeling. Although solid state diffusion kinetics dominate long-range ordering under purely thermal conditions, ordering under irradiation here (~ 2.5dpa) is controlled by the thermodynamic driving force. Finally, proton irradiation thus offers a unique approach for studying the low temperature phase transformation in a thermodynamically favored, but kinetically constrained condition.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Thermodynamic Analysis on Interactions of Silicon Dioxide with Iridium During Module Reduction and Monitoring Treatment

The goal of this paper was to understand the possible reactions between Ir and SiO 2 contaminants in the presence of C (graphite insulation) and a cover gas for conditions representative of those for a module reduction and monitoring treatment at 1410 K. This treatment is for reduction of 238 PuO 2 fuel used in isotopic heat sources for space missions. A thermodynamic analysis has been performed for the relevant portions of the Ir-Si-C-O phase diagram using the CALPHAD method. The results show that over the range of relevant pressures of CO and CO 2 in the argon cover gas, SiO 2 is not stable in the presence of Ir. Finally, levels of Si impurity dissolved in the iridium solid solution are expected to be up to 875 μg/g at or near the surface.

36 MATERIALS SCIENCE↗
DOE OSTI2018

X-ray Diffraction Investigation of Annealing Behavior of Peened Surface Deformation Layer on Precipitation Hardening Stainless Steel

In order to investigate the recrystallization behavior of peened surface deformation layer of precipitation hardening stainless steel, a classic x-ray diffraction line profile analysis, Voigt method, was carried out on peened 17-4PH with different isothermal annealing temperatures. The activation energy of domain boundary migration (Q{sub a}) and the activation energy of microstrain relaxation (Q{sub b}) were calculated by regression analysis in different annealing temperature conditions. The results show that the value of Q{sub a} decreases with annealing temperature increasing, which is due to the influence of precipitation (ε-Cu) size on the movements of grain and subgrain boundaries. The maximum growth rate of ε-Cu particles occurs during 400 to 500 °C interval. Compared with growth behavior of domain size, microstrain relaxation behavior is less sensitive to precipitation particle size. The effects of annealing temperature and time on dislocation density are both significant when annealing temperature is lower than 500 °C. However, the effect of annealing temperature on dislocation density becomes insignificant when annealing temperature is higher than 500 °C. 300 °C annealing temperature only leads to the microstrain relaxation but nearly cannot lead to the domain size growth even if prolonging annealing time. Microstructure enhancement effect still exists in plastic deformation layer when 300 °C annealing temperature lasts for 60 min but nearly disappears when 600 °C annealing temperature lasts for 20 min.

36 MATERIALS SCIENCE↗
DOE OSTI2018

High-temperature strengthening mechanisms of Laves and B2 precipitates in a novel ferritic alloy

Precipitates of the Laves and B2 phases were engineered in a newly-designed advanced ferritic alloy. Under creep test at 650 °C with 120 MPa, the material showed a steady-state minimum creep rate of 1 × 10 –4 h –1 , about one order of magnitude lower than T91. Microstructural characterization of the ferritic alloy revealed primarily ductile and partially brittle fractures after the creep test. Coarse Laves phase (~ 1 µm) was observed associating with the brittle fracture, resulting in reduced creep ductility. However, fine Laves phase precipitates (~ 100 nm) helped the dimple-ductile fracture and strengthened the material through impeding the motion of dislocations and boundaries. Unlike the B2 precipitates remained coherent exerting the classic Orowan bypassing mechanism at the brittle location, some of the B2 precipitates at the ductile location became incoherent and can develop an attractive interaction with dislocations. In conclusion, this coherency change of B2 precipitates, together with the nucleation of ultrafine (~ 40 nm) Laves phase precipitates during the creep test, would compensate for the coarsening-induced loss of Orowan strengthening of coherent B2 precipitates.

36 MATERIALS SCIENCE↗
DOE OSTI2017

Mechanical Properties and Radiation Resistance of Nanoprecipitates-Strengthened Advanced Ferritic Alloys

Five ferritic alloys and a ferritic-martensitic steel, designed by computational thermodynamics using recently developed database, were assessed in this work. A previous Fe-Cr-Zr ferritic alloy, named as Z6, was further investigated because of its amorphization behavior after a peak damage of 50 displacements per atom (dpa) at 400°C. Alloying elements of Zr, Nb, and Mo were varied to form four new ferritic alloys, named as Z1N33A, BL-Nb, BL-NbZr, and BL-Mo, which have reduced Zr-bearing Laves phase and complemented with B2-NiAl phase. The ferritic-martensitic steel, named as TTZ2M, favored MX-type (M=metal, X=C/N) precipitates with controlled M 23 C 6 and Laves phases.

36 MATERIALS SCIENCE↗
DOE OSTI2017

All‐Inorganic Bismuth‐Based Perovskite Quantum Dots with Bright Blue Photoluminescence and Excellent Stability

Abstract Lead halide perovskite quantum dots (QDs) possess color‐tunable and narrow‐band emissions and are very promising for lighting and display applications, but they suffer from lead toxicity and instability. Although lead‐free Bi‐based and Sn‐based perovskite QDs (CsSnX 3 , Cs 2 SnX 6 , and (CH 3 NH 3 ) 3 Bi 2 X 9 ) are reported, they all show low photoluminescence quantum yield (PLQY) and poor stability. Here, the synthesis of Cs 3 Bi 2 Br 9 perovskite QDs with high PLQY and excellent stability is reported. Via a green and facile process using ethanol as the antisolvent, as‐synthesized Cs 3 Bi 2 Br 9 QDs show a blue emission at 410 nm with a PLQY up to 19.4%. The whole series of Cs 3 Bi 2 X 9 (X = Cl, Br, and I) QDs by mixing precursors can cover the photoluminescence emission range from 393 to 545 nm. Furthermore, Cs 3 Bi 2 Br 9 QDs show excellent photostability and moisture stability due to the all‐inorganic nature and the surface passivation by BiOBr, which enables the one‐pot synthesis of Cs 3 Bi 2 Br 9 QD/silica composite. A lead‐free perovskite white light‐emitting diode is fabricated by simply combining the composite of Cs 3 Bi 2 Br 9 QD/silica with Y 3 Al 5 O 12 phosphor. As a new member of lead‐free perovskite QDs, Cs 3 Bi 2 Br 9 QDs open up a new route for the fabrication of optoelectronic devices due to their excellent stability and photophysical characteristics.

Leng, Meiying↗
DOE OSTI2017

Development of Computational Tools for Modeling Thermal and Radiation Effects on Grain Boundary Segregation and Precipitation in Fe-Cr-Ni-based Alloys

This work aims at developing computational tools for modeling thermal and radiation effects on solute segregation at grain boundaries (GBs) and precipitation. This report described two major efforts. One is the development of computational tools on integrated modeling of thermal equilibrium segregation (TES) and radiation-induced segregation (RIS), from which synergistic effects of thermal and radiation, pre-existing GB segregation have been taken into consideration. This integrated modeling was used in describing the Cr and Ni segregation in the Fe-Cr-Ni alloys. The other effort is thermodynamic modeling on the Fe-Cr-Ni-Mo system which includes the major alloying elements in the investigated alloys in the Advanced Radiation Resistant Materials (ARRM) program. Through thermodynamic calculation, we provide baseline thermodynamic stability of the hardening phase Ni2(Cr,Mo) in selected Ni-based super alloys, and contribute knowledge on mechanistic understanding on the formation of Ni2(Cr,Mo) in the irradiated materials. The major outcomes from this work are listed in the following: 1) Under the simultaneous thermal and irradiation conditions, radiation-induced segregation played a dominant role in the GB segregation. The pre-existing GB segregation only affects the subsequent radiation-induced segregation in the short time. For the same element, the segregation tendency of Cr and Ni due to TES is opposite to it from RIS. The opposite tendency can lead to the formation of W-shape profile. These findings are consistent with literature observation of the transitory W-shape profile. 2) While TES only affects the distance of one or two atomic layers from GBs, the RIS can affect a broader distance from GB. Therefore, the W-shape due to pre-existing GB segregation is much narrower than that due to composition gradient formed during the transient state. Considering the measurement resolution of Auger or STEM analysis, the segregation tendency due to RIS should play a dominant role in the measured values. However, The GB segregation due to pre-existing GB segregation may affect the chemical potential of element at GB, and subsequently the corrosion resistance. 3) Based on the newly developed thermodynamic database of Fe-Cr-Ni-Mo, we predicted the Ni2(Cr,Mo) as a thermodynamically stable phase in all investigated low Fe-content Ni-based alloys. The calculated phase amount decreases with the increasing Fe content, being consistent with that observed in the irradiated materials. 4) The formation of the Ni2(Cr,Mo) phase in irradiated materials is due to irradiation enhanced diffusion. The calculated equilibrium Ni2(Cr,Mo) amount is more than that observed in the irradiated materials, suggesting that the amount of Ni2(Cr,Mo) is likely to increase more with further irradiation.

36 MATERIALS SCIENCE↗
DOE OSTI2017

Phase Stability in the Fe-Rich Fe-Cr-Ni-Zr Alloys

Knowledge on phase stability in Fe-rich Fe-Cr-Ni-Zr alloys is needed for the development of Laves-phase strengthened Fe-Cr-Ni-Zr ferritic alloys which have shown promising applications as new cladding materials of nuclear reactors due to enhanced high temperature strength, and resistance to creep and irradiation hardening. Phase stability in four Fe-rich Fe-Cr-Ni-Zr alloys was carefully investigated using scanning electron microscopy, transmission electron microscopy, energy-dispersive X-ray spectroscopy and X-ray diffraction techniques. The samples were arc-melted and heat treated at 700 °C for 336 hours and 1000 °C for 1275 hours. The experimental results showed extensive solubility of Ni in the intermetallic phases Fe 23 Zr 6 and Fe 2 Zr_C15. Nickel stabilizes the Laves Fe 2 Zr_C15 structure more than the C36 and C14 structures. In addition to Fe 23 Zr 6 and Fe 2 Zr_C15, Ni 7 Zr 2 was found to be stable in samples with higher Ni content and lower annealing temperature. The body-centered-cubic, Fe 2 Zr_C15 and Fe 23 Z 6 coexist in all samples regardless of composition and temperature. Detailed analysis suggested that the coexistence of these three phases is not a result of thermodynamic equilibrium, but a result of the competing formation kinetics of Fe 2 Zr_C15 and Fe 23 Z 6 .

36 MATERIALS SCIENCE↗
DOE OSTI2017

Microstructural evolution of neutron-irradiated T91 and NF616 to ~4.3 dpa at 469 °C

Ferritic-martensitic steels such as T91 and NF616 are candidate materials for several nuclear applications. Here, this study evaluates radiation resistance of T91 and NF616 by examining their microstructural evolutions and hardening after the samples were irradiated in the Advanced Test Reactor to ~4.3 displacements per atom (dpa) at an as-run temperature of 469 °C. In general, this irradiation did not result in significant difference in the radiation-induced microstructures between the two steels. Compared to NF616, T91 had a higher number density of dislocation loops and a lower level of radiation-induced segregation, together with a slightly higher radiation-hardening. Unlike dislocation loops developed in both steels, radiation-induced cavities were only observed in T91 but remained small with sub-10 nm sizes. Lastly, other than the relatively stable M 23 C 6 , a new phase (likely Sigma phase) was observed in T91 and radiation-enhanced MX → Z phase transformation was identified in NF616. Laves phase was not observed in the samples.

36 MATERIALS SCIENCE↗
DOE OSTI2017

Integrated modeling of second phase precipitation in cold-worked 316 stainless steels under irradiation

The current work combines the Cluster Dynamics (CD) technique and CALPHAD-based precipitation modeling to address the second phase precipitation in cold-worked (CW) 316 stainless steels (SS) under irradiation at 300–400 °C. CD provides the radiation enhanced diffusion and dislocation evolution as inputs for the precipitation model. The CALPHAD-based precipitation model treats the nucleation, growth and coarsening of precipitation processes based on classical nucleation theory and evolution equations, and simulates the composition, size and size distribution of precipitate phases. We benchmark the model against available experimental data at fast reactor conditions (9.4 × 10 –7 dpa/s and 390 °C) and then use the model to predict the phase instability of CW 316 SS under light water reactor (LWR) extended life conditions (7 × 10 –8 dpa/s and 275 °C). The model accurately predicts the γ' (Ni 3 Si) precipitation evolution under fast reactor conditions and that the formation of this phase is dominated by radiation enhanced segregation. The model also predicts a carbide volume fraction that agrees well with available experimental data from a PWR reactor but is much higher than the volume fraction observed in fast reactors. We propose that radiation enhanced dissolution and/or carbon depletion at sinks that occurs at high flux could be the main sources of this inconsistency. The integrated model predicts ~1.2% volume fraction for carbide and ~3.0% volume fraction for γ' for typical CW 316 SS (with 0.054 wt% carbon) under LWR extended life conditions. Finally, this work provides valuable insights into the magnitudes and mechanisms of precipitation in irradiated CW 316 SS for nuclear applications.

36 MATERIALS SCIENCE↗
DOE OSTI2017

The Prediction of Long-Term Thermal Aging in Cast Austenitic Stainless Steel

Cast austenitic stainless steel (CASS) materials are extensively used for many massive primary coolant system components of light water reactors (LWRs) including coolant piping, valve bodies, pump casings, and piping elbows. Many of these components are operated in complex and persistently damaging environments of elevated temperature, high pressure, corrosive environment, and sometimes radiation for long periods of time. Since a large number of CASS components are installed in every nuclear power plant and replacing such massive components is prohibitively expensive, any significant degradation in mechanical properties that affects structural integrity, cracking resistance in particular, of CASS components will raise a serious concern on the performance of entire power plant. The CASS materials for nuclear components are highly corrosion-resistant Fe-Cr-Ni alloys with 300 series stainless steel compositions and mostly austenite (γ)–ferrite (δ) duplex structures, which result from the casting processes consisting of alloy melting and pouring or injecting liquid metal into a static or spinning mold. Although the commonly used static and centrifugal casting processes enable the fabrication of massive components with proper resistance to environmental attacks, the alloying and microstructural conditions are not highly controllable in actual fabrication, especially in the casting processes of massive components. In the corrosion-resistant Fe-Cr-Ni alloy system, the minor phase (i.e., the δ-ferrite phase) is inevitably formed during the casting process, and is in a non-equilibrium state subject to detrimental changes during exposure to elevated temperature and/or radiation. In general, relatively few critical degradation modes are expected within the current design lifetime of 40 years, given that the CASS components have been processed properly. It has been well known, however, that both the thermal aging and the neutron irradiation can cause degradation of static and impact toughness in the cast stainless steels, and if combined with any flaws formed during the fabrication process or in service, the thermal degradation in CASS components can be a serious concern for the integrity of the power plant. On the integrity of the CASS components during the extended lifetime of 60 years or longer, no conclusive prediction has been possible, primarily because no direct experience with these materials currently exists, and the aging behavior of CASS alloys still remains largely uncertain. The ongoing research for CASS aging, as part of the LWRS Program/Materials Aging and Degradation Pathway, is an integrated research using holistic experimental and modeling means to provide both the scientific understanding on the aging and failure phenomena and the practical models to predict the degree of property degradation.

cast stainless steels↗