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At least 1,099 records · Page 61

Calculations of the moon's heat history at different concentrations of radioactive elements taking account of the material differentiation with melting

A mathematical procedure for analyzing the heat conductivity of the lunar surface is discussed. The solution is based on homogeneous and laminated moon models and considers the effects of radioactive elements conveyed to the lunar surface by melting. The various parameters which introduce uncertainties into the numerical analysis are identified. The application of data obtained from radio astronomy and from analyses of lunar samples returned by the Apollo flights is explained. Tables of data are included to show the types and amounts of radioactive materials which have been identified.

Arnatskaya, O. I.↗

Search for and analysis of radioactive halos in lunar material

The lunar halo search was conducted because halos in terrestrial minerals serve as pointers to localized radioactivity, and make possible analytical studies on the problems of isotopic dating and mode of crystallization of the host mineral. Ancillary studies were conducted on terrestrial halos and on certain samples of special origin such as tektites and meteorites.

Gentry, R. V.↗

Alkaline earth ion exchange study in pure silica LTA zeolites using periodic first-principles calculations

Experiments show that Zeolites, such as Linde Type A (LTA), are promising materials for radioactive decontamination processes. In this work, the thermodynamic properties associated with alkaline earth ion (Ca2+, Sr2+ and Ba2+) exchange in pure silica LTA was studied using periodic first-principles calculations. The adsorption energies of alkaline earth ions compared with that of Na+ were investigated. The driving force for the alkaline earth exchange and related isotherms were calculated, and analyzed as a function of the electron chemical potential. The results demonstrate that Na+ in a pure silica LTA can completely be removed by Ba2+ and almost completely be removed by Sr2+ from a stream, but cannot be effectively exchanged by Ca2+. We also showed that electron-donating dopants should suppress the Sr2+ and Ba2+ ion exchange, and that there is a substantial preference for incorporating Ba2+ over Sr2+. Lastly, the substantial difference between the adsorption energies of the ions in an assumed vacuum and those computed in water suggests that a solvation model is needed for accurate representation of ion adsorption in an LTA zeolite.

Kocevski, Vancho↗

A new ordered triple Hollandite: Ba{sub 1.33}Sb{sub 2.66}Al{sub 5.33}O{sub 16}

Ba{sub 1.33}Sb{sub 2.66}Al{sub 5.33}O{sub 16} is a triple Hollandite, which crystallizes in a tetragonal cell (I4/m no. 87) with a=b=9.86090(5) A and c=8.77612(6) A. Its crystal structure was characterized using electron diffraction and X-ray powder diffraction; it is isotypic to K{sub 1.33}Mg{sub 3.11}Sb{sub 4.89}O{sub 16}, K{sub 1.76}Mg{sub 3.25}Sb{sub 4.75}O{sub 16} and to K{sub 1.8}Li{sub 2.45}Sb{sub 5.55}O{sub 16}. In the rutile chains of Ba{sub 1.33}Sb{sub 2.66}Al{sub 5.33}O{sub 16}, the ordering of Al and Sb atoms into unmixed sites induces the tripling of the c parameter compared to a 'single' Hollandite structure. The Ba{sup 2+} cations are dispersed along c, in the largest tunnels on non-split and fully occupied sites. They lie into Ba-Ba pairs separated by vacancies. Their regular arrangement has been confirmed by high resolution electron microscopy. Electrochemical experiments have also been performed in Li-ion cell but no Li insertion was detected. - Graphical Abstract: The new Ba{sub 1.33}Sb{sub 2.66}Al{sub 5.33}O{sub 16} triple Hollandite has been synthesized and characterized by X-ray diffraction, electron microscopy, and cyclic voltammetry. Highlights: > Synthesis of a new barium antimonium aluminium oxide with a Hollandite structure. > X-ray diffraction, electron microscopy and cyclic voltammetry studies. > Presence of cationic vacancies but no Li insertion activity.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Vehicle Radiation Monitoring Systems for Medical Waste Disposal - 12102

Hospitals often declare their waste as being 'non-radioactive'; however this material often has excessive levels of radiation caused either by an accident or lack of control. To ensure the best possible protection against the accidental receipt of radioactive materials and as a safety precaution for their employees, waste-handling companies have installed large-scale radiation portal monitors at their weigh scales or entry gates of the incinerator plant, waste transfer station, and/or landfill. Large-volume plastic scintillator-based systems can be used to monitor radiation levels at entry points to companies handling medical waste. The recent and intensive field tests together with the thousands of accumulated hours of actual real-life vehicle scanning have proven that the plastic scintillation based system is an appropriate radiation control instrument for waste management companies. The Real-Time background compensation algorithm is flexible with automatic adjustable coefficients that will response to rapidly changing environmental and weather conditions maintaining the preset alarm threshold levels. The Dose Rate correction algorithms further enhance the system's ability to meet the stringent requirements of the waste industries need for Dose Rate measurements. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Water retention and gas relative permeability of two industrial concretes

This experimental study aims at identifying the water retention properties of two industrial concretes to be used for long term underground nuclear waste storage structures. Together with water retention, gas transfer properties are identified at varying water saturation level, i.e. relative gas permeability is assessed directly as a function of water saturation level S{sub w}. The influence of the initial de-sorption path and of the subsequent re-saturation are analysed both in terms of water retention and gas transfer properties. Also, the influence of concrete microstructure upon water retention and relative gas permeability is assessed, using porosity measurements, analysis of the BET theory from water retention properties, and MIP. Finally, a single relative gas permeability curve is proposed for each concrete, based on Van Genuchten-Mualem's statistical model, to be used for continuous modelling approaches of concrete structures, both during drying and imbibition.

36 MATERIALS SCIENCE↗

Why SRS Matters – SRNL Part 1

A video series presenting an overview of the Savannah River Site's (SRS) mission and operations. Each episode features a specific area/operation and how it contributes to help make the world safer.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Simulations of Sparse Static Detector Networks for City-Scale Radiological/Nuclear Detection

Sparse static detector networks in urban environments can be used in efforts to detect illicit radioactive sources, such as stolen nuclear material or radioactive "dirty bombs." We use detailed simulations to evaluate multiple configurations of detector networks and their ability to detect sources moving through a $6\times 6$ km 2 area of downtown Chicago. A detector network's probability of detecting a source increases with detector density but can also be increased with strategic node placement. Here, we show that the ability to fuse correlated data from a source-carrying vehicle passing by multiple detectors can significantly contribute to the overall detection probability. In this article, we distinguish static sensor deployments operated as networks able to correlate signals between sensors, from deployments operated as arrays where each sensor is operated individually. In particular, we show that additional visual attributes of source-carrying vehicles, such as vehicle color and make, can greatly improve the ability of a detector network to detect illicit sources.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Simultaneous {sup 233}U and{sup 235}U characterization through the assay of delayed neutron temporal behavior

Aqueous solutions containing dissolved uranium-233 and uranium-235 were irradiated for 60's in the SLOWPOKE-2 reactor at the Royal Military College of Canada. The temporal behavior of the delayed neutrons produced was recorded by the Facility's Delayed Neutron Counting (DNC) system. The percentage of uranium-233 as a function of total fissile mass present in each sample ranged from 0 to 100% and was predicted by the DNC system with average absolute errors of {+-} 4%. Future work will upgrade the system electronics and software to reduce both uncertainties in timings and electrical noise. Mixture analysis will also be expanded to include plutonium-239 and fissile materials contained in non-aqueous matrices. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Choosing the Best Modeling Platform for Radiological Risk Assessment Models - 20468

Radiological risk assessments, in the form of performance or safety assessments, are often required under regulations or guidance for remediation of contaminated land, decommissioning of contaminated buildings or structures, and radioactive waste disposal. These risk assessments are usually supported by fate and transport models that address decay and ingrowth of radionuclides, as well as their movement through engineered systems and the natural environment. These models are often projected thousands, or more, years into the future, largely because the radioactive species change through decay and ingrowth, and hence the magnitude of the radioactive effect changes with time. There are many computer codes that are available to address this type of modeling. They range from addressing specific pathways or processes such as infiltration of water, groundwater, surface water, air, biota, diffusion and advection of water and gases, to those that try to couple all processes together to evaluate the impact of fate and transport through the entire system to places in space and time to which access is assumed. These different types of codes are sometimes separated with the monikers process-level and systems-level codes, although it is often not clear that this separation does justice to the capabilities of the many codes that are available to evaluate fate and transport of radionuclides. The focus of this paper is the latter group of modeling codes. Several systems level modeling codes exist and are used. There are differences between these codes in terms of utility, flexibility, complexity and cost. The purpose of this paper is to compare a few of these codes in the context of work currently being performed by the International Atomic Energy Agency (IAEA) Modeling and Data for Radiological Impact Assessments (MODARIA) II Working Group 1 (WG1). The MODARIA II WG1's main focus is how stakeholder engaged decision analysis can, or should, be applied to radiological contamination problems so that better, longstanding, sustainable, solutions are reached. However, the WG1 also recognizes the potential impact of the modeling tools that are chosen to address radiological risk, which is often a primary objective of decision making for radiological problems. Other objectives might also be important, such as constraining costs, obtaining financing, minimizing impact on ecosystems, saving cultural resources, saving jobs, farmland, environmental justice, etc., in a full decision analysis for a given radiological contamination problem, but none of these other objectives have the same types of complex modeling needs as minimize radiological dose. Consequently, a further focus of WG1 is to evaluate the potential impacts on decision making of the choice of fate and transport, and risk assessment, modeling codes that are used to support decision making. The WG1 will produce a report at the end of 2020 that will focus on an approach to effective decision making and stakeholder engagement. The report will also consider the role that performance assessment modeling should play in the decision-making process, including the impact of the choice of modeling tools or computer codes on risk-informed decision making. Several sites around the World have been made available by Member States for these model comparisons, and several modeling tools have been considered. However, the focus of this paper is on two of the sites, one in Belgium and one in Ukraine, and on three of the tools: NORMALYSA (NORM And Legacy Site Assessment); GoldSim{sup C}, and AMBER{sup C}. The final report from this working group will also cover other modeling tools, including RESRAD, and PC-Cream{sup R}. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

A novel approach for enhanced visible light activity in doped nanosize titanium dioxide through the excitons trapping

Titanium dioxide doped with iron oxide (0-10 mol%) has been synthesized by an aqueous sol-gel method. The extent of phase transformation is higher in presence of up to 1 mol% of Fe{sup 3+} ions in doped titania. A further increase in Fe{sup 3+} content was found to decrease the phase transformation. A composition which contains {approx}90% rutile and the remaining anatase phase shows the highest photocatalytic activity. Even though surface area values are dramatically decreased by the modification of TiO{sub 2} by Fe{sup 3+} doping, crystallinity plays a major role in photocatalytic activity enhancement. UV-vis reflectance spectra indicate a red-shift in band gap energy and thus an enhanced photoactivity in visible light, suitable for application in photodegradation of toxic industrial effluents as well as other organic contaminants, is achieved. Low concentrations of Fe{sup 3+} ions act as excitons trapping centers, while higher concentrations act as recombination centers. The synergy between the rutile-anatase ratios and optimum amount of Fe{sup 3+} ions improve the interfacial charge transfer and trapping which enhanced the photochemical degradation of MB dye. The Fe{sup 3+} doped TiO{sub 2} composition has the highest photoactivity, having an apparent rate constant of 11.1 Multiplication-Sign 10{sup -3} min{sup -1}, which is much higher than that of commercial P25 Degussa titania (6.03 Multiplication-Sign 10{sup -3} min{sup -1}). - Graphical abstract: Model explaining the transfer and trapping of e{sup -}/h{sup +} pairs in mixed phase titania by Fe{sup 3+} ions suggests the reason for the increased lifetime of e{sup -}/h{sup +} pairs and enhanced photocatalytic activity. Highlights: Black-Right-Pointing-Pointer An aqueous sol-gel method for the preparation of doped TiO{sub 2} is being reported. Black-Right-Pointing-Pointer High photocatalytic activity and simplicity are the novelty of this work. Black-Right-Pointing-Pointer Enhanced activity is explained by the mechanism of trapping of charges.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

[La(UO{sub 2})V{sub 2}O{sub 7}][(UO{sub 2})(VO{sub 4})] the first lanthanum uranyl-vanadate with structure built from two types of sheets based upon the uranophane anion-topology

The new lanthanum uranyl vanadate divanadate, [La(UO{sub 2})V{sub 2}O{sub 7}][(UO{sub 2})(VO{sub 4})] was obtained by reaction at 800 Degree-Sign C between lanthanum chloride, uranium oxide (U{sub 3}O{sub 8}) and vanadium oxide (V{sub 2}O{sub 5}) and the structure was determined from single-crystal X-ray diffraction data. This compound crystallizes in the orthorhombic system with space group P2{sub 1}2{sub 1}2{sub 1} and unit-cell parameters a=6.9470(2) A, b=7.0934(2) A, c=25.7464(6) A, V=1268.73(5) A{sup 3}, Z=4. A full matrix least-squares refinement yielded R{sub 1}=0.0219 for 5493 independent reflections. The crystal structure is characterized by the stacking of uranophane-type sheets {sup 2}{sub {infinity}}[(UO{sub 2})(VO{sub 4})]{sup -} and double layers {sup 2}{sub {infinity}}[La(UO{sub 2})(V{sub 2}O{sub 7})]{sup +} connected through La-O bonds involving the uranyl oxygen of the uranyl-vanadate sheets. The double layers result from the connection of two {sup 2}{sub {infinity}}[La(UO{sub 2})(VO{sub 4}){sub 2}]{sup -} sheets derived from the uranophane anion-topology by replacing half of the uranyl ions by lanthanum atoms and connected through the formation of divanadate entities. - Graphical abstract: A view of the three-dimensional structure of [La(UO{sub 2})V{sub 2}O{sub 7}][(UO{sub 2})(VO{sub 4})]. Highlights: Black-Right-Pointing-Pointer New lanthanum uranyl vanadate divanadate has been synthesized. Black-Right-Pointing-Pointer Structure was determined from single-crystal X-ray diffraction data. Black-Right-Pointing-Pointer Structure is characterized by uranophane-type sheets and double layers {sup 2}{sub {infinity}}[La(UO{sub 2})(V{sub 2}O{sub 7})]{sup +}.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Development of In-Situation Radioactivity Inspection System for Food Materials

The impacts on the ocean of releases of radionuclides from the Fukushima nuclear power plants remain unclear. Korean people worry about radioactive contamination of Japanese and Korean sea products. Radioactive contamination of processed foodstuffs, livestock, sea products, farm products imported from Japan and fishes caught in coastal oceans of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary/middle/high school and university. Radioactivity inspections of food materials have been executed manually with portable measuring instruments or at labs using their samples. But, it's very important the radioactivity inspection should be performed at the field of feeding facilities. To protect the health of people from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time has been developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs or school. The performance test of NaI(Tl) detector was examined using the quantified Cs-137 source 10 Bq/kg, 30 Bq/kg, 50 Bq/kg, 300 Bq/kg and 900 Bq/kg at Korea Research Institute of Standards and Science(KRISS). Source was put in a box and radioactivity was measured in the middle of the box. First of all, Background was measured and calibration was performed using the Cs-137 300 Bq and Ba-133 3700 Bq for 60 minutes. After setting the background and calibration data, tests of the Cs-137 10, 30, 50, 300, 900 Bq/kg were executed for 10 minutes. A peak-shaped graph is shown at the location of 662 KeV (80∼100 channel). This is due to the gamma radiation energy with 662 KeV emitted by the Cs-137. Because through KRISS examination, the MDA (minimum detectable activity) is about 23 Bq/kg, it is reasonable Cs-137 10 Bq/kg cannot be measured. And in cases of Cs-137 300 Bq/kg and 900 Bq/kg, there are some peak movement on the graph. It can be adjusted by controlling gain or high voltage. The examination was identified through the performance test (Cs-137 10, 30, 50, 300, 900 Bq/kg) at KRISS. In order to increase the measurement efficiency of Cs-137 and the system performance, database will be built up based on radioactivity measurement results from 10 to 300 Bq/kg with the unit 10. Thus, Cs-137 concentration of food materials can be identified below the maximum permissible concentration of 100 Bq/kg on a basis of the spectrum characteristic of Cs-137. Also, anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and trust of the radioactive inspection is expected definitely. (authors)

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

An international initiative on long-term behavior of high-level nuclear waste glass

Nations using borosilicate glass as an immobilization material for radioactive waste have reinforced the importance of scientific collaboration to obtain a consensus on the mechanisms controlling the long-term dissolution rate of glass. This goal is deemed to be crucial for the development of reliable performance assessment models for geological disposal. The collaborating laboratories all conduct fundamental and/or applied research using modern materials science techniques. This paper briefly reviews the radioactive waste vitrification programs of the six participant nations and summarizes the current state of glass corrosion science, emphasizing the common scientific needs and justifications for on-going initiatives.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Phase composition and magnetic properties of niobium-iron codoped TiO{sub 2} nanoparticles synthesized in Ar/O{sub 2} radio-frequency thermal plasma

Nanoparticles of Nb{sup 5+}-Fe{sup 3+} codoped TiO{sub 2} with various Nb{sup 5+} concentrations (Nb/(Ti+Fe+Nb)=0-10.0 at%) and Fe{sup 3+} (Fe/(Ti+Fe+Nb)=0-2.0 at%) were synthesized using Ar/O{sub 2} thermal plasma. Dopant content, chemical valence, phase identification, morphology and magnetic properties were determined using several characterization techniques, including inductively coupled plasma-optical emission spectrometer, X-ray photoelectron spectroscopy, X-ray diffraction, UV-vis diffuse reflectance spectrometer, field-emission scanning electron microscopy, transmission electron microscopy and SQUID commercial instrument. The XRD revealed that all the plasma-synthesized powders were exclusively composed of anatase as major phase and rutile. The rutile weight fraction was increased by the substitution of Fe{sup 3+} for Ti{sup 4+} whereas it was reduced by the Nb{sup 5+} doping. The plasma-synthesized Nb{sup 5+}-Fe{sup 3+} codoped TiO{sub 2} powders had intrinsic magnetic properties of strongly paramagnetic and feebly ferromagnetic at room temperature. The ferromagnetic properties gradually deteriorated as the Fe{sup 3+} concentration was decreased, suggesting that the ferromagnetism was predominated by the phase composition as a carrier-mediated exchange. - Graphical Abstract: Spherical nanoparticles of Nb{sup 5+}-Fe{sup 3+} codoped TiO{sub 2} were synthesized using Ar/O{sub 2} thermal plasma. The plasma-synthesized powders were composed of anatase as major phase and rutile. Rutile weight fraction was increased by Fe{sup 3+} addition but was reduced by Nb{sup 5+} doping. Strongly paramagnetic and feebly ferromagnetic properties are of intrinsic nature. Ferromagnetic properties gradually deteriorated as Fe{sup 3+} concentration was increased. Highlights: > Nanoparticles of Nb{sup 5+}-Fe{sup 3+} codoped TiO{sub 2} were synthesized using Ar/O{sub 2} thermal plasma. > The plasma-synthesized powders were composed of anatase as major phase and rutile. > Rutile weight fraction was increased by Fe{sup 3+} addition but was reduced by Nb{sup 5+} doping. > Strongly paramagnetic and feebly ferromagnetic properties are of intrinsic nature. > Ferromagnetic properties gradually deteriorated as Fe{sup 3+} concentration was increased.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Phase stability of some actinides with brannerite structure at high pressures

Structure behavior of actinide brannerites ThTi{sub 2}O{sub 6}, Y{sub 0.5}U{sub 0.5}Ti{sub 1.5}Nb{sub 0.5}O{sub 6} and their analog oxide CeTi{sub 2}O{sub 6} was studied at high pressure by using in situ x-ray diffraction, Raman scattering and infra-red absorption techniques, respectively. Brannerite structure was found to be not stable and started to become amorphous at pressures above 20 GPa. Some minor crystalline phase(s) due to phase decomposition was observed in all the three samples during pressurization. In addition, the observed bulk modulus indicated that the actinide-bearing brannerites are more compressible than their analog compound CeTi{sub 2}O{sub 6}, which may be related to the asymmetric 5f electron orbits of actinide elements. - Graphical abstract: Actinide-bearing compounds with brannerite structure and their analog CeTi{sub 2}O{sub 6} are not stable at high pressure. They were amorphized after {approx}20 GPa and a minor pressure-induced phase transition or decomposition process was always observed before amorphization. Highlights: > Phase stability of three brannerites CeTi{sub 2}O{sub 6}, ThTi{sub 2}O{sub 6}, and (U,Y)(Ti,Nb){sub 2}O{sub 6} at high pressures. > Brannerite structure was not stable and became amorphous after {approx}20 GPa. > Actinide-bearing brannerites are easier compressed than their analog compound CeTi{sub 2}O{sub 6}.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Methods of capturing and immobilizing radioactive nuclei with metal fluorite-based inorganic materials

Methods of capturing and immobilizing radioactive nuclei with metal fluorite-based inorganic materials are described. For example, a method of capturing and immobilizing radioactive nuclei includes flowing a gas stream through an exhaust apparatus. The exhaust apparatus includes a metal fluorite-based inorganic material. The gas stream includes a radioactive species. The radioactive species is removed from the gas stream by adsorbing the radioactive species to the metal fluorite-based inorganic material of the exhaust apparatus.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗