AVS 66 Session AC-MoA: Early Career Scientists

Monday, October 21, 2019 1:40 PM in Room A215

Monday Afternoon

Session Abstract Book
(282KB, Apr 26, 2020)
Time Period MoA Sessions | Abstract Timeline | Topic AC Sessions | Time Periods | Topics | AVS 66 Schedule

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1:40 PM AC-MoA-1 Advanced Characterization of Nuclear Fuels
Lingfeng He, Tiankai Yao (Idaho National Laboratory); Vinay Chauhan (The Ohio State University); Amrita Sen (Purdue University); Zilong Hua, Mukesh Bachhav (Idaho National Laboratory); Marat Khafizov (The Ohio State University); Janelle Wharry (Purdue University); Matthew Mann (Air Force Research Laboratory); Thierry Wiss (European Commission, Joint Research Centre (JRC)); Jian Gan, David Hurley (Idaho National Laboratory)

Oxide nuclear fuels have been widely used in light water reactors. The thermal conductivity of nuclear fuels is closely related to energy conversion efficiency as well as reactor safety. Understanding the mechanisms that cause the degradation in thermal conductivity in a high radiation environment is important for the design and development of new high-burnup fuels. For oxide nuclear fuels, phonon scattering by point defects, extended defects such as dislocation loops and bubbles, and grain boundaries plays a significant role in limiting the thermal transport properties. In this work, detailed microstructural characterization of pristine and ion irradiated ThO2 and UO2 has been performed by using electron backscatter diffraction (EBSD), atomic-resolution scanning transmission electron microscope (S/TEM), atom probe tomography (APT) and time-domain Brillouin scattering (TDBS) techniques. The thermal conductivity before and after irradiation has been determined using laser-based modulated thermoreflectance (MTR) technique. This work is partially supported by the Center for Thermal Energy Transport under Irradiation, an Energy Frontier Research Center funded by the U.S. Department of Energy Office of Sciences.

2:20 PM AC-MoA-3 The Influence of Relative Humidity on the Oxidation of δ-Pu
Scott Donald, Jeff Stanford, Art Nelson, Bill McLean (Lawrence Livermore National Laboratory)

The evolution of delta stabilized plutonium aged under a controlled environment composed of laboratory air and a range of relative humidities up to 95% was studied using Auger electron spectroscopy (AES). Linear-least squares analysis was performed on AES spectra acquired during Ar+ sputter depth profiles to gain insight on the thickness and any variation in the chemical speciation of the oxide. Sputter rates were calibrated from depth profiles obtained from an oxide of a known thickness from FIB/SEM measurements. At all relative humidities, the initial oxide layer was found to grow logarithmically, indicative of a diffusion-controlled process. The rate of oxide growth was also found to be independent of oxygen partial pressure (for pO2 > 31.5 Torr) for all conditions studied.

The work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

3:00 PM AC-MoA-5 Magnetization and Transport Properties of Delta Phase Uranium
Xiaxin Ding, Narayan Poudel, Tiankai Yao, Jason Harp, Krzysztof Gofryk (Idaho National Laboratory)

At room temperature, uranium metal is in its alpha form, the most common structural form of the element. It consists of corrugated sheets of atoms in an asymmetrical orthorhombic structure. However, the room temperature stabilized delta phase can be formed by alloying uranium with zirconium, which is known to have hexagonal crystal structure. It is important to know the physical properties of U-Zr alloys due to their technological importance. In this talk, we will present the first-time results of magnetization, transport and thermodynamic measurements of delta phase uranium at low temperatures and under high magnetic fields. The results obtained help us to understand the 5f ground state properties in different phases of U. We will discuss implications of these results.

3:20 PM AC-MoA-6 Using Fused Filament Fabrication to Develop Customized Materials which Attenuate Ionizing Radiation
Zachary Brounstein, Eamonn Murphy, Joseph Dumont, Samantha Talley, Kwan Lee, Andrea Labouriau (Los Alamos National Laboratory)

Ionizing radiation is of serious consideration in the nuclear industry because protecting workers and instrumentation is of utmost concern when operating equipment that emits potentially hazardous radiation. Currently, commercial products are readily used as protective barriers, but there are circumstances when these are less than ideal at providing optimal shielding against neutrons and gamma rays[1],[2]. As innovations to nuclear energy technologies continue to progress, developing new materials for radiation shielding grows in importance and need.

In the present work, we used an additive manufacturing (AM) technique known as Fused Filament Fabrication (FFF) to create novel 3D printed materials for radiation shielding. FFF is a layered AM process whereby thermoplastic filaments are heated up to their melting point and extruded into cross-sections of the end product[3],[4]. Because FFF has the capability to create prototypes and end-use parts with fine resolution details and excellent strength-to-weight ratios, the technology is used throughout aerospace, automotive, and medical industries.

Difficulties in creating filaments for FFF arise from fabricating a homogeneous wire that has uniform thickness and a smooth surface. If a filament does not have these initial properties, then either the FFF process will not work or the end product will not be as desired. Creating a homogeneous wire proves more difficult when different base and filler materials are used in the fabrication process, however, this can be solved if the different materials are combined in a liquid solution. Creating a wire of uniform thickness relies heavily on the extrusion process, whereby the temperature and extrusion speed are controlled.

In this study, we have prepared homogeneous filaments with varying processing conditions such as the contribution of additives and the control of extrusion temperature and speed. Thus, we used FFF to create novel filaments to print sheets of customized materials for attenuating ionizing radiation. Irradiating the printed samples was performed at the Los Alamos Neutron Science Center and the Gamma Irradiation Facility by bombarding the customized materials with neutrons and gamma rays, respectively.

References

1. McAlister, D.R., Gamma Ray Attenuation Properties of Common Shielding Materials. PG Research Foundation, Inc., 2018. Revision 6.1.

2. Shin, J.W., et al, Thermochimica Acta, 2014. 585: p. 5-9.

3. Guo, N. and M.C. Leu, Frontiers of Mechanical Engineering, 2013. 8(3): p. 215-243.

4. Srivatsan, T.S. et al, Additive Manufacturing: Innovations, Advances, and Applications. CRC Press. 2016. p. 1-48.

3:40 PM BREAK
4:00 PM AC-MoA-8 Thermodynamic and Thermal Transport Properties of Thorium Dioxide single crystals
Narayan Poudel, Xiaxin Ding (Idaho National Laboratory); James M Mann (Air Force Research Laboratory); Krzysztof Gofryk (Idaho National Laboratory)

Thorium dioxide (ThO2) crystalizes into CaF2-type (fluorite) cubic structure, similar to other members of AnO2 (An = Th-Am) family. Thorium dioxide forms stoichiometrically and is a wide-gap transparent insulator (Eg~5-6 eV). This material is used as nuclear fuel in certain types of nuclear reactors (CANDU) that might have more advantages than conventional UO2 based nuclear reactors. It is because of its higher thermal conductivity, higher corrosion resistance, and higher melting point. Despite its importance in nuclear technology, the thermodynamic and thermal transport properties of ThO2 single crystals have not been studied extensively, especially at low temperatures where many different scattering mechanisms such as boundary, defects, and/or phonon-phonon dominate the heat transport. In this talk, we will present our recent measurements of the heat capacity and thermal conductivity of ThO2 single crystals, obtained from room temperature down to 2 K. Large and good quality single crystals of ThO2 have been synthesized by hydrothermal method for this study. We will also compare the result obtained on ThO2 to UO2, especially in the context of impact of 5f-electrons on thermodynamic and transport behavior in these materials.

4:20 PM AC-MoA-9 Magnetic Nanoparticles for Biomedical Applications
Iliana Medina-Ramirez, Alejandra Diaz de Leon Olmos (Universidad Autonoma de Aguascalientes, Mexico); Juan Antonio Zapien (City University of Hong Kong)

Magnetic nanostructured materials (MNMs) are attractive candidates for biomedical applications because of the highly desirable advantages of magnetic-guided targeting. Furthermore, MNMs can be produced by simple fabrication processes that enable flexibility to modulate their properties and desired bio-activity.

The simultaneous optimization of the bio-activity of interest while simultaneously preventing, or at least minimizing, deleterious side effects is of the outmost importance for critical applications such as the development of magnetic hyperthermia cancer treatment. However, this requires more complex multi-criteria optimization studies. We use Fe3O4 and CoFe2O4 MNMs prepared by microwave solvothermal method and a citrate surface modification, to modulate their toxicity and stability, as model systems to develop protocols for optimization of therapeutic MNMs. The interaction of surface-modified MNMs with HepG2 cells is evaluated by colorimetric, optical microscopy and Atomic Force Microscopy (AFM) studies for dose. We show that AFM presents important advantages over conventional techniques including information on the potential internalization of MNMs by the cells as function of surface modification. The optimized MNMs in this study present morphological, colloidal, biocompatibility and magnetic properties that make them promising candidates for the development of efficient therapeutic agents for hyperthermia cancer treatment applications.

Session Abstract Book
(282KB, Apr 26, 2020)
Time Period MoA Sessions | Abstract Timeline | Topic AC Sessions | Time Periods | Topics | AVS 66 Schedule