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At least 1,513 records · Page 84

Determination of Method Detection Limits for Trace 232-Thorium and 238-Uranium in Copper using Ion Exchange and ICPMS

Based on the MAJORANA DEMONSTRATOR (MJD) simulations task group calculations, the copper used in the inner shield and detector components require purity levels of <0.3 µBq 238 U/kg Cu and <0.3 µBq 232 Th/kg Cu. The MAJORANA Collaboration is endeavoring to achieve this goal by electroforming copper using ultra-clean materials in facilities at PNNL and SURF. In this document, a broadly accepted U.S. Environmental Protection Agency method is used to evaluate an ion exchange technique, developed at PNNL, for determining sensitivity in the assay of copper for trace levels of thorium and uranium. These data indicate that, in all cases, the assay sensitivity and material limits are being met.

Hoppe, Eric W.↗

Simulation of xenon, uranium vacancy and interstitial diffusion and grain boundary segregation in UO 2

In light water reactor fuel, gaseous fission products segregate to grain boundaries, resulting in the nucleation and growth of large intergranular fission gas bubbles. Based on the mechanisms established from density functional theory (DFT) and empirical potential calculations 1, continuum models for diffusion of xenon (Xe), uranium (U) vacancies and U interstitials in UO 2 have been derived for both intrinsic conditions and under irradiation. Segregation of Xe to grain boundaries is described by combining the bulk diffusion model with a model for the interaction between Xe atoms and three different grain boundaries in UO 2 ( Σ5 tilt, Σ5 twist and a high angle random boundary),as derived from atomistic calculations. All models are implemented in the MARMOT phase field code, which is used to calculate effective Xe and U diffusivities as well as redistribution for a few simple microstructures.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Development of Advanced High Uranium Density Fuels for Light Water Reactors

This work conducts basic materials research (fabrication, radiation resistance, thermal conductivity, and corrosion response) on U3Si2 and UN, two high uranium density fuel forms that have a high potential for success as advanced light water reactor (LWR) fuels. The outcome of this proposed work will serve as the basis for the development of advance LWR fuels, and utilization of such fuel forms can lead to the optimization of the fuel performance related plant operating limits such as power density, power ramp rate and cycle length.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Final Report DE-SC0006997; PI Sharp; Coupled Biological and Micro-XAS/XRF Analysis of In Situ Uranium Biogeochemical Processes

Project Overview: The impact of the original seed award was substantially increased by leveraging a postdoctoral fellowship (Marie Curie Postdoctoral Fellowship) and parallel funds from (A) synergistic project supported by NSF and (B) with DOE collaborators (PI’s Ranville and Williams) as well as no-cost extension that greatly increased the impact and publications associated with the project. In aligning with SBR priorities, the project’s focus was extended more broadly to explore coupled biogeochemical analysis of metal (im)mobilization processes beyond uranium with a foundation in integrating microbial ecology with geochemical analyses. This included investigations of arsenic and zinc during sulfate reducing conditions in addition to direct microbial reduction of metals. Complimentary work with NSF funding and collaborative DOE interactions further increased the project scope to investigate metal (im)mobilization coupled to biogeochemical perturbations in forest ecosystems with an emphasis on coupled carbon and metal biogeochemistry. In total, the project was highly impactful and resulted in 9 publications and directly supported salary/tuition for 3 graduate students at various stages of their academic careers as well as my promotion to Associate Professor. In going forward, findings provided inspiration for a two subsequent proposals with collaborators at Lawrence Berkeley Laboratory and others that are currently in review (as of March 2016).

54 ENVIRONMENTAL SCIENCES↗

Procedure for Uranium-Molybdenum Density Measurements and Porosity Determination

The purpose of this document is to provide guidelines for preparing uranium-molybdenum (U-Mo) specimens, performing density measurements, and computing sample porosity. Typical specimens (solids) will be sheared to small rectangular foils, disks, or pieces of metal. A mass balance, solid density determination kit, and a liquid of known density will be used to determine the density of U-Mo specimens using the Archimedes principle. A standard test weight of known density would be used to verify proper operation of the system. By measuring the density of a U-Mo sample, it is possible to determine its porosity.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

2015 Uranium Mill Tailings Radiation Control Act (UMTRCA) Title ll Annual Report, L-Bar, New Mexico Disposal Site

The L-Bar, New Mexico, Uranium Mill Tailings Radiation Control Act (UMTRCA) Title II Disposal Site was inspected on August 18, 2015. The tailings impoundment was in excellent condition. Erosion and vegetation measurements to monitor the condition of the impoundment cover indicated that no erosion is occurring, and perennial vegetation foliar cover at the measurement plots increased substantially compared to previous years due to above-average precipitation for the year. A short segment of the perimeter fence near the site entrance was realigned in spring 2015 because a gully was undermining the fence corner. Loose fence strands at another location were repaired during the inspection, and a section of fence needs to be realigned to avoid areas affected by deep gullies and sediment deposition. Inspectors identified no other maintenance needs or cause for a follow-up inspection. Groundwater monitoring is required every 3 years. The next monitoring event will be in 2016.

54 ENVIRONMENTAL SCIENCES↗

Comparison Of A Neutron Kinetics Parameter For A Polyethylene Moderated Highly Enriched Uranium System

This paper examines the comparison of MCNP® code’s capability to calculate kinetics parameters effectively for a thermal system containing highly enriched uranium (HEU). The Rossi-α parameter was chosen for this examination because it is relatively easy to measure as well as easy to calculate using MCNP®’s kopts card. The Rossi-α also incorporates many other parameters of interest in nuclear kinetics most of which are more difficult to precisely measure. The comparison looks at two different nuclear data libraries for comparison to the experimental data. These libraries are ENDF/BVI (.66c) and ENDF/BVII (.80c).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Proposal for Monitoring Within the Centrifuge Cascades of Uranium Enrichment Facilities

Safeguards are technical measures implemented by the International Atomic Energy Agency (IAEA) to independently verify that nuclear material is not diverted from peaceful purposes to weapons (IAEA, 2017a). Safeguards implemented at uranium enrichment facilities (facilities hereafter) include enrichment monitors (IAEA, 2011). Figure 1 shows a diagram of how a facility could be monitored. The use of a system for monitoring within centrifuge cascades is proposed.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Non-invasive acoustic-based monitoring of uranium in solution and H/D ratio

The primary objective of this project is to adapt existing non-invasive acoustic techniques (Swept-Frequency Acoustic Interferometry and Gaussian-pulse acoustic technique) for the purpose of demonstrating the ability to quantify U or H/D ratios in solution. Furthermore, a successful demonstration will provide an easily implemented, low cost, and non-invasive method for remote and unattended uranium mass measurements for International Atomic Energy Agency (IAEA).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Production of Low Enriched Uranium Nitride Kernels for TRISO Particle Irradiation Testing

A large batch of UN microspheres to be used as kernels for TRISO particle fuel was produced using carbothermic reduction and nitriding of a sol-gel feedstock bearing tailored amounts of low-enriched uranium (LEU) oxide and carbon. The process parameters, established in a previous study, produced phasepure NaCl structure UN with dissolved C on the N sublattice. The composition, calculated by refinement of the lattice parameter from X-ray diffraction, was determined to be UC 0.27 N 0.73 . The final accepted product weighed 197.4 g. The microspheres had an average diameter of 797±1.35 μm and a composite mean theoretical density of 89.9±0.5% for a solid solution of UC and UN with the same atomic ratio; both values are reported with their corresponding calculated standard error.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Mechanical Behavior of Additively Manufactured Uranium-6 wt. pct. Niobium

This report describes an effort to process uranium-6 weight% niobium using laser powder bed fusion. The chemistry, crystallography, microstructure and mechanical response resulting from this process are discussed with particular emphasis on the effect of the laser powder bed fusion process on impurities. In an effort to achieve homogenization and uniform mechanical behavior from different builds, as well as to induce a more conventional loading response, we explore post-processing heat treatments on this complex alloy. Elevated temperature heat treatment for recrystallization is evaluated and the effect of recrystallization on mechanical behavior in laser powder bed fusion processed U-6Nb is discussed. Wrought-like mechanical behavior and grain sizes are achieved through post-processing and are reported herein.

36 MATERIALS SCIENCE↗

Dr. Ian Hutcheon Award Spectroscopic Fingerprinting of Vapor-Phase Uranium Species

The Dr. Ian Hutcheon Post-Doctoral Fellowship provides resources to fund a TNFapplicable research project as well as promote mentorship, career development, and relevant training for the recipient. The two-year proposal incorporated a research plan to investigate uranium chemistry relevant to post-detonation nuclear forensics and a mentorship plan to address career development for the recipient in TNF-relevant areas.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

Advanced Characterization of Microwave Melt Cast Uranium

For the last decade, the use of microwave (MW) melting and casting technology for processing uranium (U) has been under development at Y-12 National Security Complex in Oak Ridge, TN [2] . Their objective has been to determine if MW is a viable option to replace conventional vacuum induction melting (VIM) for some U part types. Some of the benefits of using MW technology are minimizing processing steps and decreasing impurity content by changing crucible material, which will help to lower costs and improve machinability, respectively. While Y-12 has shown success using a MW melting and casting process to make U parts [4, 5], it is still a relatively new technology for casting metals, and there are several unknowns with respect to how the material properties compare to conventional VIM cast U. One major concern, associated with MW casting of metals, is superheating, which can cause arcing or plasma formation in a part and result in non-uniform material properties. Therefore, studying the anisotropy in MW cast metals in terms of pertinent properties is highly relevant. Specifically, the properties of interest here are deformation behavior and mechanical properties of U tested at different strain rates and weldability of thin wall sections. In order to address concerns about high strain rate mechanical properties, prototype MW-U parts (processed in 2009) were sent to LLNL in 2015 for advanced materials testing. The parts received had relatively thin walls (~6 mm), so Split Hopkinson Pressure Bar was selected as a method for dynamic mechanical testing (strain rate of ~103s-1) since most other high-rate (HR) tests require much larger sample dimensions. A VIM-U part from Y-12 was not available at the time of the study, so a VIM part from Idaho National Laboratory, cast into a rectangular block, was used here for comparison.

36 MATERIALS SCIENCE↗

Optimized Dissolution Flowsheet for Uranium Metal

The U.S. Department of Energy’s National Nuclear Security Administration (NNSA) has entered into cooperative agreements with commercial businesses to establish a reliable domestic source of 99 Mo that will be produced without the use of highly enriched uranium (HEU).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Additive Manufacturing of a y0-Tetragonal Uranium-Niobium Alloy

The ability to process near-net shape structures is of particular interest in applications using rare or expensive materials. Laser powder bed fusion additive manufacturing can meet this challenge, yet also introduces significant processing and materials challenges toward achieving structural integrity. Broadly addressed aspects affecting powder bed fusion structures include surface roughness, residual stresses, and porosity. Here, we focus on materials-specific challenges—namely, the influence of multiple pass reheating during processing and post-processing homogenization on phase transformations and the role of impurities and oxides on grain morphology and mechanical behavior—with a view of adopting laser powder bed fusion processing for the shape memory alloy, uranium-6 wt.% niobium. Our observations to date on the factors influencing material behavior and post-processing requirements and recommendations for process improvement are discussed herein.

36 MATERIALS SCIENCE↗