bluuebunny/crossref_metadata_2025_split huggingface dataset:
Polymeric Nanoscale All-Solid State Battery
Authors: Bullock Steven E. , Kofinas Peter 
Published: April 2011

AbstractThe advent of polymer electrolytes has provided a promising route to an all solid-state polymer battery. Such a battery would have greater safety, without potential discharge of liquid or gel electrolyte. Current battery configurations typically involve a metal anode, a solvent-plasticized polyelectrolyte, such as poly (ethylene oxide) (PEO), and a composite cathode. We have synthesized an A/B/C triblock copolymer which could have potential use as an all-solid state nanoscale polymer lithium battery. The polymeric battery was synthesized with an anode, electrolyte and cathode by synthesizing an A/B/C triblock copolymer whose microphase separation would form lamellar domains. These nanodomains contain cobalt oxide, a derivative of PEO synthesized by ring opening metathesis polymerization, and a spinel phase LiMn2O4 as the anode, electrolyte and cathode material, respectively. The first block contains cobalt oxide that stores lithium ion in a novel electrochemical reaction that allows use in a battery configuration. The second block is polyethylene oxide derived from an unsaturated crown ether, and is used for its high ionic conductivity. The third block contains LiMn2O4, which is currently being investigated as a potential cathode material because of its low toxicity and ease of preparation. The nanometer size domains in the battery can be used in unique applications in microelectronics. In addition, such size scale allows use of the battery in discrete circuits, reducing the amount of wiring necessary in conventional battery configurations.
Hole Transport In Self-Organized Oligosilane Thin Films With Highly Ordered Hopping Sites
Authors: Okumoto H. , Yatabe T. , Richter A. , Shimomura M. , Kaito A. , Minami N. 
Published: April 2011

ABSTRACTSelf-organized oligosilane thin films possess molecular orientation normal to substrates with multilayered structure. This unique order of -conjugated molecules results in good hole transport properties. In the present work, carrier transport properties at low temperature are studied for 1,10-diethyldecamethylsilane polycrystalline films. Even at a temperature as low as 173 K, a time-of-flight transient photocurrent waveform showed a clear plateau and a sharp decay, whose shape is similar to that at room temperature. Their hole mobility followed Arrhenius type temperature dependence with a small activation energy of 0.09 eV. The hole mobility of 6.3×10-5cm2/Vs at 193 K was more than 2 orders of magnitude higher than that of typical polysilanes, which inevitably contain disordered structures hindering smooth carrier transport.
Electrophosphorescent Light Emitting Devices Using Mixed Ligand Ir(III) Complexes
Authors: Lee Hae Won , Das R. R. , Lee Chang-Lyoul , Noh Yong-Young , Kim Jang-Joo 
Published: April 2011

ABSTRACTWe have fabricated phosphorescent light emitting devices using mixed ligand bisorthometalated Ir(III) complexes, chlorobis-(2-phenylpyridinato-N,C2')pyridineiridium(III) [Ir(Cl)(ppy)2(py)] and chlorobis-(2-phenylpyridinato-N,C2')triphenylphosphine iridium(III) [Ir(Cl)(ppy)2P(Ph)3] chlorobis-(2-phenylpyridinato-N,C2')tri-n-butylphosphine iridium(III) [Ir(Cl)(ppy)2P(n-Bu)3], where ppy is the orthometalating ligand. These complexes vary in their HOMO (highest occupied molecular orbital), LUMO (lowest unoccupied molecular orbital) and emissive states in accordance with the φ-accepting abilities of the non-orthometalating ligands. The lifetimes and EL spectrum of the devices were studied and compared.
Structural Dependence and Dynamics of White Luminescence in Multilayer Structures for White Organic Light Emitting Devices
Authors: Fujita Shizuo , Uesaka Ken-ichi , Fujita Shigeo 
Published: April 2011

ABSTRACTWhite electroluminescence (EL) spectra are carefully investigated in terms of the multilayer structures and a rule for designing the white luminescence is discussed. For a simple structure which consists of tris(8-hydroxyquinoline)-aluminum (Alq) and 1,2,3,4,5-pentaphenyl-1,3-cyclopendadiene (PPCP) emitting green and blue luminescence, respectively, as luminescent and electron transport layers, white luminescence appeared if the thickness of each layer was appropriately chosen. The luminescence efficiency was higher in PPCP, and therefore one of the structures effectively emitting white luminescence was designed as PPCP(10 nm)/Alq(40 nm). The 4-(dicyanomethylene)-2-methyl-6-(p-dimethylaminostyryl)-4H-pyran (DCM) was then added to the PPCP/Alq structure intending to enhance red luminescence. We propose the structure where red luminescence is from the DCM as photoluminescence excited by the green and blue luminescence from Alq and PPCP, which was effective, compared to the PPCP/Alq/DCM stacking structure, in avoiding increase of the operating voltage. The importance of designing structures of organic white EL devices based on fundamental optical properties of the constituent layers and on luminescence dynamics is highlighted.
A 2” monochrome 64×96 passive matrix PLED
Authors: Huiberts Hans , Weijer Peter van de , Büchel Michael , Kok Margreet de , Vulto Simone , Meulenkamp Eric , Haskal Eliav 
Published: April 2011

ABSTRACTRoyal Philips Electronics has recently launched the first commercially available polymer Light Emitting Diode (LED). In this paper, physical properties and phenomena will be discussed that must be taken into account during the selection of a polymer material and the choice of the device structure; for example, color, electron and hole mobility, polymer thickness, lifetime, leakage current and failure.
Three-Color Passive-Matrix Pixels Using Dye-Diffusion-Patterned Tri-Layer Polymer-Based LED
Authors: Long Ke , Pschenitzka Florian , Sturm J. C. 
Published: April 2011

ABSTRACTDry dye-printing and solvent-enhanced dye diffusion were used to locally dope a previously spin-coated poly(9-vinylcarbazole) (PVK) polymer film with different dyes to fabricate side-by-side RGB OLED pixels. To reduce reverse leakage current and raise efficiency, a blanket tris-8-hydroxyquinoline aluminum (Alq) electron transport layer (ETL) was deposited over the polymer layer after the dye diffusion step, along with a 2,9-dimethyl-4,7-diphenyl-1,10-phenanthroline (BCP) hole/exciton blocking layer between the Alq and the PVK to ensure all light emission occurred from the doped polymer and not from the Alq. Devices with this tri-layer structure have an extremely low reverse leakage current (rectification ratio of 106 at +/- 10V) and a higher external quantum efficiency (∼1%) than single layer devices. A three-color passive-matrix test array with 300μm x 1mm RGB subpixels was demonstrated with this structure.
Photonic Crystals at Near-Infrared and Optical Wavelengths
Authors: Moroz Alexander 
Published: April 2011

ABSTRACTAs demonstrated for the example of a diamond and zinc blende structure of dielectric spheres, small inclusions of a low absorbing metal with the volume fraction fm can have a dramatic effect on a complete photonic band gap (CPBG) between the 2nd-3rd bands. For example, in the case of silica coated silver spheres, the CPBG opens for fm ≍ 1.1% and exceeds 5% for fm ≍ 2.5%. Consequently, any dielectric material can be used to fabricate a photonic crystal with a sizeable and robust CPBG in three dimensions. Absorption in the CPBG of 5% remains very small (≥ 2.6% for λ ≥ 750 nm). The structure enjoys almost perfect scaling, enabling one to scale the CPBG from microwaves down to ultraviolet wavelengths.
Deliquescence Behavior of Multicomponent Salts: Effects on the Drip Shield and Waste Package Chemical Environment of the Proposed Nuclear Waste Repository at Yucca Mountain, Nevada
Authors: Pabalan Roberto T. , Yang Lietai , Browning Lauren 
Published: April 2011

ABSTRACTThermodynamic calculations were conducted to determine the deliquescence behavior of salt mixtures and to simulate the evaporation of Yucca Mountain groundwaters. The results are consistent with published experimental data that show the deliquescence points of salt mixtures are lower than that of individual salts. For mixtures of NaCl and KCl salts, the deliquescence point of pure NaNO3 salt is an appropriate lower bound. However, mixtures containing magnesium and calcium salts have much lower deliquescence points than pure NaNO3. If magnesium and calcium salts are deposited on waste package and drip shield surfaces, it could lead to earlier initiation of aqueous corrosion than assumed by the DOE in its performance assessment abstractions. Such salt mixtures can be formed by evaporation of waters with compositions similar to some Yucca Mountain porewaters and would be characterized by low deliquescence relative humidity, high chloride concentration, and low concentrations of anions such as free (uncomplexed) nitrate and sulfate that could mitigate against the chloride-enhanced corrosion of the waste package. Evaporation of Yucca Mountain groundwaters also could lead to fluoride concentrations that are above the threshold for accelerated corrosion of the titanium drip shield.
Effects of Fluoride and Chloride Ions on Corrosion of Titanium Grade 7 in Concentrated Groundwaters
Authors: Pulvirenti A. L. , Needham K. M. , Adel-Hadadi M. A. , Barkatt A. 
Published: April 2011

ABSTRACTTitanium Grade 7 (Ti-7) was tested for both general and local corrosion in environments consisting of fluoride and chloride salts added to simulated groundwaters. Tests were conducted on both U-bends and disks in order to determine the extent of corrosion under stressed and unstressed conditions. The experiments were run over a broad range of temperatures and pH values for periods of up to 164 days. It was found that Ti-7 is susceptible to intergranular attack in some of the test solutions at moderately elevated temperatures, leading to conspicuous localized corrosion. Pitting was detected within 14 days, with pit depths on the order of 0.1 mm. Surface defects appeared to promote the initiation of pitting. The same environment caused stress corrosion cracking failure in a statically stressed U-bend.
Synthesis and Characterization of Cubic Zirconia, (Zr,Gd,Pu)O2, Doped with 238Pu
Authors: Burakov Boris E. , anderson Evgeniy B. , Zamoryanskaya Maria V. , Yagovkina Maria A. , Nikolaeva Elena V. 
Published: April 2011

ABSTRACTCrystalline ceramic materials based on the cubic zirconia structure have been proposed as candidate waste forms for the immobilization of weapons grade Pu and other actinides. To evaluate a resistance of these materials to self-irradiation for extended period of time, polycrystalline samples of gadolinia-stabilized cubic zirconia, (Zr,Gd,Pu)O2, doped with approximately 10 wt.% 238Pu were synthesized and characterized. Ceramic synthesis was done by sintering in air at 1500°C for 4 hours using starting precursor materials based on coprecipitated and then calcined oxalates of Zr, Gd, Pu. No differences were observed among the zirconia X-ray diffraction patterns that were obtained immediately after ceramic synthesis, or at 88 and 201 days later. MCC-1 leach tests were performed on ceramic specimens in deionized water at 90°C for 28 days. It was found that without correction for ceramic porosity the initial Pu mass loss (NL) was 0.04 g/m2. This increased to 0.35 and 0.37 g/m2, respectively, 180 and 260 days later. Results obtained allow us to confirm that actinide-doped cubic zirconia is highly resistant to accelerated self-irradiation and therefore, is an efficient material for actinide immobilization in deep geological repositories.
Sensitivity Studies of the Effect of Cladding Degradation on TSPA Results
Authors: Siegmann Eric , Devonec Eve 
Published: April 2011

ABSTRACTThe Commercial Spent Nuclear Fuel (CSNF) cladding directly influences the dose by reducing the release rate of radionuclides compared to bare fuel. A cladding degradation model was introduced in the Total System Performance Assessment – Viability Assessment (TSPA-VA) and has evolved into the TSPA-SR (Sight Recommendation), Rev 00 and most recently the Supplemental Science and Performance Analyses (SSPA) models. TSPAs are large computer models that predict how the radionuclides might escape through the various barriers and migrate through the different geological regions and predict the dose to the critical population. The major components in the cladding degradation model are initial cladding failure, creep, stress corrosion cracking (SCC), localized corrosion, mechanical failures (due to seismic events and rock overburden) and cladding unzipping. In the bare fuel case, the dose is controlled by the failure rate of the waste packages (WPs), the solubility limits for certain radionuclides, and the rate of diffusion of the radionuclides through the cracks in the WPs. The cladding degradation model involves two steps, perforation followed by unzipping. Sensitivity studies have shown that cladding limits dose primarily by preventing dissolution of the UO2 fuel (when the cladding is not perforated). If all the cladding is assumed to be perforated and cladding unzipping occurs, the peak dose would be within 4% of that of bare fuel. The UO2 dissolution rate (the driving mechanism for cladding unzipping) is sufficiently rapid that assuming instant dissolution increases the dose by only 12% from the base case. In the current cladding degradation model, cladding accounts for a reduction in dose for the first 100,000 years of a factor of 16 when compared with bare fuel. This is because of the low initial cladding failure rate (2.1% including SCC and creep) and few failures from localized corrosion (late WP breach and limited water entering the WPs). Failure of the cladding by rock overburden accounts for an increasing trend in dose at times greater than 100,500 years. This mechanism increases the peak dose and delays the peak from approximately 200,000 to 300,000 years. In conclusion, the cladding degradation model, mostly through preventing water from contacting the UO2, reduces the dose predicted in the TSPA analysis.
Investigation of the Oxidation State of Uranium in Nuclear Materials and their Alteration Products
Authors: Buck Edgar C. , Colella Michael , Smith Katherine L. , Lumpkin Gregory R. 
Published: April 2011

ABSTRACTIn this study, the oxidation state of uranium was investigated with Electron Energy-Loss Spectroscopy on the Transmission Electron Microscope. The oxygen K edge in a series of uranium-bearing phases was investigated and this technique was compared to an alternative method of using the relative intensities of the M4,5- edges of the actinides. Under controlled conditions, it is possible to obtain reliable oxidation state data on uranium solids; however, mixtures of oxidation states in a single compound cannot be distinguished with certainty.
Creep Analyses of Titanium Drip Shield Subjected to Rockfall Static Loads in the Proposed Geologic Repository at Yucca Mountain
Authors: Neuberger Brett W. , Greene Charles A. , Gute G. Douglas 
Published: April 2011

ABSTRACTThe U.S. Department of Energy (DOE) has included a drip shield (DS) as a principle component of the engineered barrier system (EBS) for the proposed high-level nuclear waste geologic repository at Yucca Mountain, Nevada. The current DS design consists of titanium grade 7 (Ti Gr 7) plates and Ti Gr 24 support beams and bulkheads. The intended functions of the DS are to divert dripping water around and prevent rockfall damage to the waste package (WP). Sustained static loading of the DS may occur as a result of rockfall or drift collapse. These static loads may cause residual stress that approaches the yield stresses of the different DS materials. This level of residual stress would enable various creep mechanisms to transpire. A preliminary assessment of the potential for DS creep after a dynamic rock block impact is presented in this paper by expressing the DS residual Von Mises stress levels as fractions of the Ti alloy yield stress (YS). It was determined, using creep data from similar alloys that the residual stress levels within a DS after a 2-tonne rock block impact per DS segment length could cause creep in both the Ti Gr 7 plates and Ti Gr 24 bulkheads and support beams. The results of this study will assist the U.S. Nuclear Regulatory Commission (NRC) in evaluating the risk significance of the expected DS performance characteristics under actual repository conditions.
Corrosion Behavior of Carbon Steel in Bicarbonate (HCO3) Solutions
Authors: Dong Junhua , Nishimura Toshiyasu , Kodama Toshiaki 
Published: April 2011

ABSTRACTCarbon steel is considered in Japan the most promising candidate material for overpacks in high-level radioactive waste disposal. Effects of bicarbonate solutions on the corrosion behavior and corrosion products of carbon steel were investigated by electrochemical measurements; FT-IR spectra and XRD pattern analyses. The results of the anodic polarization measurements showed that bicarbonate (HCO3) accelerates the anodic dissolution and the outer layer film formation of carbon steel in the case of high concentrations, whereas it inhibits these processes in the case of low concentrations. The FTIR and XRD analyses of the anodized film showed that siderite (FeCO3) was formed in 0.5 to 1.0mol/L bicarbonate solution, and Fe2(OH)2CO3 in 0.1 to 0.2mol/L bicarbonate solution, while Fe6(OH)12CO3 was formed in 0.02 to 0.05mol/L bicarbonate solution. In all cases the pH value was around 8.3. The stability of these chemical compositions was discussed using a potential – pH diagram for the Fe-H2O-CO2 system.
Proof-of-Concept Flowsheet Tests for Cesium Removal from Tank Waste by Caustic-Side Solvent Extraction
Authors: Chamberlain David B. , Aase Scott , Arafat Hassan A. , Conner Cliff , Leonard Ralph A. , Regalbuto Monica C. , Vandegrift George F. 
Published: April 2011

ABSTRACTA caustic-side solvent extraction (CSSX) process to remove cesium from Savannah River Site (SRS) high-level waste has been developed through a joint program with Oak Ridge National Laboratory (ORNL), the Savannah River Technical Center (SRTC), and Argonne National Laboratory (ANL). The CSSX solvent consists of four components: (1) an extractant, a calixarene crown, calix[4]arene-bis(tert-octylbenzo-crown-6) designated BOBCalixC6, (2) a modifier, an alkyl aryl polyether, 1-(2,2,3,3,-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol, also called Cs-7SB, (3) a suppressant, an alkyl amine, trioctylamine (TOA), and (4) a diluent, Isopar®L. The solvent composition is 0.01 M BOBCalixC6, 0.50 M Cs-7SB, and 0.001 M TOA in Isopar®L. In this program we have developed and demonstrated a flowsheet that can be used to process SRS tank waste. To this end, a series of flowsheet tests were completed using simulated waste in a 2-cm centrifugal contactor at ANL. Three short-term (3-4 hours) tests were completed to demonstrate various aspects of the flowsheet. These tests were followed by a 71-h test where the solvent was recycled 42 times. In each case, we met or exceeded the key process goals: (1) cesium removal from the waste with a decontamination factor greater than 40,000, (2) concentration of cesium in the aqueous strip effluent by a factor of 15 using dilute nitric acid, and (3) stripping the solvent sufficiently to allow it to be recycled many times. The results from the 71-h test are discussed.
Synthesis and Evaluation of Uranium and Thorium Imprinted Resins
Authors: Noyes K.L. , Draye M. , Favre-Réguillon A. , Foos J. , Guy A. , Czerwinski K.R. 
Published: April 2011

ABSTRACTIon exchange resins were created to complex either UO22+ or Th4+ from aqueous solutions. The nitrate salt of the target metal ion was dissolved in CCl2H2, while the resin was created around the ions to provide a unique structure based upon each metal. These resins were synthesized by a radical polymerization method, producing a reusable organic solid. The resins were qualified by obtaining values for their proton exchange capacities and data to define their complexation kinetics. Proton exchange capacities were determined using an indirect titration and were found to be 6.40 meq/g for the uranium-based resin and 4.61 meq/g for the thorium-based resin. Data for the resins' kinetics were obtained at pH 1.0, 2.5, 4.0, and 5.5. Results show that the templated resin rapidly removed the target actinides from aqueous solution under experimental conditions. Once loaded with metal, the ions can easily be removed with 5 M HNO3 and reused.
Effects of Reactor Decontamination Complexing Agents On Soil Adsorption-Column Studies (JJ5.4)
Authors: Serne R. J. , Cantrell K. J. , Kutnyakov I. V. , Lindenmeier C. W. 
Published: April 2011

ABSTRACTPrevious studies show that some radionuclides present in reactor decontamination wastes form strong complexes with the organic complexing agents used to decontaminate reactor cores and piping. Further, the metal-ligand complexes exhibit reduced adsorption to soils. Flow through column tests were used to study the adsorption of metal-organic ligand complexes to two soils. The breakthrough curves for metals and organic ligands for four tests are shown. In all the column tests, the adsorption of the organic ligand-metal complex, or the free organic ligand and free metal (disassociated species) was reversible. That is, close to the total mass injected was recovered in the flushing stage with untraced background solution.Two tests that used the iron oxide coated sand show complicated behavior that was interpreted as being caused by ligand (both EDTA and picolinate) interacting with the ferric oxides. The Ni-organic ligand complex in both cases appears to exchange Ni for Fe to some extent such that free Ni+2is produced and Fe (III)-organic complexes are formed that adsorb with different strengths. Further, we suspect that the organic ligand is dissolving some of the ferric oxide coatings and destroying sorption sites. The combination of all these reactions leads to rather complicated breakthrough curves. In tests with picolinate there is partial disassociation of the metal and ligand such that the breakthrough curves for the metal and ligand are differentA recommendation is made to not bury EDTA-laden decontamination wastes with cement. Another observation is that predictions that use simple constant Kdand constant source release constructs may not be exclusively conservative in predicting concentrations of contaminants in water down-gradient from disposal sites.
Durability of Pu-doped Titanate and Zirconate Ceramics Designed for Pu Immobilisation
Authors: Zhang Y. , Hart K.P. , Begg B.D. , Keegan E.A. , Day A.R. , Brownscombe A. , Stewart M.W.A. 
Published: April 2011

ABSTRACTCeramics rich in pyrochlore-structured titanate and fluorite-structured zirconate phases designed for surplus Pu immobilisation, with and without process impurities, have been leach tested at 90°C in deionised water. The zirconates consist mainly of a defect-fluorite with secondary impurity-containing phase-powellite/scheelite (when sintered in Ar but not when sintered in air), a spinel or magnetoplumbite type phase, a glass forming silicate and a secondary U-rich phase (when sintered in air with added impurities). The pyrochlore-rich baseline titanate ceramic consists of pyrochlore, brannerite and Hf-rutile. When impurities are added zirconolite and a silicate glass are also present. The pyrochlore-rich titanate with 5 wt% of impurities sintered at 1300°C is highly durable. A well-densified zirconate version without impurities has comparable elemental releases to those of the titanate ceramic but a zirconate with 5 wt% of impurities sintered at 1400°C in air or Ar shows much higher U and Ca releases than the titanate ceramic. Sintering atmospheres, changing from Ar to air, can influence Pu and U release rates up to an order of magnitude. High Ga releases from zirconates with impurities show that the secondary phase containing Ga is not durable. The higher processing temperature and the apparent inability to incorporate many impurity elements suggest that zirconates are not as flexible as titanates in respect of processing conditions and aqueous durability.