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At least 181 records · Page 10

Chemical Modeling of the Capture of Radioiodine Species

Iodine is a common fission product resulting from the transmutation of uranium fuel in nuclear power reactors. The short-lived radioactive isotope, 131 I, with a half-life of around eight days, would be a particular health concern if released into the environment. Capture materials, such as activated carbon, are used routinely in nuclear power plants and medical isotope production facilities to remove this hazard during normal operations to reduce emissions to acceptable levels. Iodine, unlike other common fission products such as noble gases, is challenging because of the wide range of molecular forms and oxidation states (from +VII in IF 7 to -I in iodide) that it displays, which can interconvert both in the gas phase and in the solution phase for example. The work in this project is focused on three computational tasks. In the first, we consider the binding of iodine-containing molecules of varying oxidation states to the major component of activated carbon – pristine graphene-like sheets. The second task focused on molecular binding and possible chemical transformations resulting from the reaction of molecular iodine with chemical functional groups on the edge of the graphene sheets or surface defects in the sheet itself. The final task was associated with radiolytic breakdown of 131 I to 131 Xe in iodine containing molecules and investigated the resulting molecular fragmentation process both in the gas phase and on the graphene-like surface. For each of the tasks, the intent was to learn about the thermodynamics and kinetics of the chemical transformations and use the calculations to provide parameters for input into kinetic models describing these processes for interpretation of experimental data in future work.

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Molybdenum Recovery from Filters Used in Large-scale Dissolution of Sintered Mo-disks

99 Mo production with linear accelerators can be achieved via the bremsstrahlung photonuclear reaction 100 Mo(γ,n) 99 Mo or the neutron capture reaction 98 Mo(n,γ) 99 Mo. For commercial producers, maximum recovery of enriched 98 Mo and 100 Mo target material is critical for sustaining an economic production cycle. During the peroxide dissolution of Mo metal disks and subsequent conversion to K 2 MoO 4 , several grams of Mo can be lost during filtration from solution when several hundred grams of sintered Mo disks are processed. This investigation shows that 5–8 g Mo is routinely retained on the filter units, but it can be almost fully recovered using aqueous washes. Washing can be done immediately and incorporated into the dissolution procedure, or it can occur several months after the initial filtration process to decrease processing time.

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Hydrogen isotope fractionation using graphene and related 2-D materials. Final report

This report provides a final technical report and listing of products from the research on a research project from Clemson university, focused on use of two-dimensional materials within membranes to accomplish hydrogen ion separations. The project used CVD graphene and related 2D materials to accomplish hydrogen / deuterium / tritium (H/D/T) separation during water electrolysis in proton-exchange-membrane (PEM)-style cells. 2D materials were incorporated into PEM cells at varying places with the aim of accomplishing isotopic sieving through 2D materials by selective hydron transport at high rates and with high selectivity. The project work scope included studies on H/D separation with small-scale cells at Clemson, collaborative work between Clemson and SRNL on computational modeling and tritium separations, and issues associated with scaleup.

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Development and Optimization of a Purification Process to Recover 99 Mo from Low-enriched Uranium

Supported by the DOE-NNSA Office of Material Management & Minimization (M3), a number of domestic entities are pursuing non-highly enriched uranium (non-HEU) production of 99 Mo. As the production technologies of 99Mo pivot toward low-enriched uranium (LEU) or molybdenum targets, new reaction channels and accelerators are being evaluated. Superconducting electron linear accelerators (LINACs) with high-Z converter targets can generate bremsstrahlung photons and neutron fluxes that are capable of inducing photonuclear reactions and LEU fission. A particular advantage of a LINAC is that it does not rely on HEU-fueled reactor cores (which are currently slated for LEU conversion) and can operate on an almost continuous basis. Regarding the chemical purification of 99 Mo from irradiated uranium targets under acidic digestion, there exists a procedure known as Cintichem or modifications thereof with respect to LEU (LEU Modified Cintichem process, LMC). The process relies on a number of selective precipitation steps and column chromatography to purify Mo. It is important to note that LMC prescribes the addition of stable Mo to carry 99 Mo on alpha benzoin oxime, which reduces the specific activity of 99 Mo. This is especially important for processing 99 Mo batches with lower activities (~33 Ci of 99 Mo per batch).

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Monitoring Radiochemical Processing Streams for the 238 Pu Supply Program with Process Pulse II

Oak Ridge National Laboratory (ORNL) is developing advanced spectroscopic and real-time monitoring capabilities to improve the timeliness of analytical measurements and process decisions for the 238Pu Supply Program. Reducing the time, resources, and costs associated with each production campaign is critical because overlapping campaigns will be required to meet the production goals of the National Aeronautics and Space Administration. Real-time, in situ analytical measurements in the heavily shielded hot cells at the Radiochemical Engineering Development Center (REDC) will allow for rapid process information feedback and operational benefits that help the 238Pu supply program scale-up production efforts. Noteworthy steps were taken during Campaign 5 to establish the ability to monitor processing streams in real time with spectrophotometry and a commercially available online monitoring software called The Unscrambler X Process Pulse II (PP) multivariate statistical process monitoring system by Camo Analytics (version 5.60). PP automates univariate-type calculations within the software itself and executes multivariate models built using The Unscrambler X (version 10.4 or newer). The Unscrambler is a commercially available data analysis software made by the same company. PP is composed of easy-to-use-tools for all personnel, including data scientists and technicians. The software can be used to plot analyte concentration profiles, spectral data, and other process variables in real time. All process data are represented in a single view with interactive charts useful for viewing how a process evolves over time.

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Building Assessment of Radon Reduction Interventions with Energy Retrofits Expansion (The BEX Study): Final Report

This report presents the findings from a study that was performed to assess whether current precautionary measures used by the US Department of Energy Weatherization Assistance Program (WAP) are effective for preventing indoor radon increases following weatherization. The study results show that current practices have produced substantial benefit compared to previous practices, and that there are no statistically significant changes in indoor radon levels on the lowest living levels with these practices following weatherization.

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Export Administration Regulations (EAR) and Radiation Tolerant Microelectronics

Sandia National Laboratories was asked to provide a technical feasibility assessment on whether programmability is a viable means to address the radiation levels in the Export Administration Regulations (EAR). Most (if not all) modern Complementary Metal Oxide Semiconductor (CMOS) technologies will exceed at least one of the EAR radiation criteria inherently, there is no longer anything “special” about domestic parts or technologies that exceed EAR radiation criteria. A modern part today is not “designed” to exceed EAR criteria and in fact a part would need to be “specially designed” to fail to meet all of these criteria. And although it is possible to design a part to fail to meet the EAR radiation criteria in an unprogrammed state, such a part would be difficult to design in some technologies, may not achieve the ultimate radiation levels desired, would fail to meet core reliability principles, and may be unsuitable for high consequence applications.

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Boson Fermion Nucleus And Previous Research On Alpha Clustering And Tetrahedral Structure In The Nucleus: Monograph #9

For 80 years, the presence of alpha clusters in nuclei and nuclei with tetrahedral structures has been studied in theory and researched in experiment. Scattering experiments have detected alpha clusters in heavy nuclei. The theoretical treatment of this evidence has considered close-packed alpha clusters bound together in stable nuclear structures throughout the periodic table. While alpha clusters have been conceived as linear two-dimensional and three-dimensional close-packed, crystal-like structures, theorists have not considered three-dimensional extended structures as exhibited by boson fermion nuclei (BFNs). BFNs are composed of alphas and the nuclei of hydrogen, deuterium, tritium, and helium-3 as building blocks. Previous theoretical and experimental work has shown correspondence with the 6 Li, 7 Li, 10 B, 11 B, and 40 Ca BFN.

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Boson Fermion Nuclei And Structures Throughout The Periodic Table Of Elements: Monograph #8

A homologous structural pattern among nuclei that corresponds to the periodicity of the periodic table of elements has been identified. Schematic diagrams of boson fermion nuclei (BFN) are shown for nuclei throughout the periodic table of elements. Transition elements in the fourth, fifth, and sixth periods display bridges between the legs of the tetrahedral nuclear structure, occurring where the nuclear structure is sufficiently massive to create potential wells able to hold the nucleons in a fermion-pocket quantum system bridging the legs. These nuclei are not formed by buildup, as in stepwise nuclear fusion or nucleon capture, but by a process in which the nucleus has “fallen down” in mass during stellar nucleosynthesis from a higher A and Z, shedding nucleons and decaying radioactively to arrive at a lowest-energy-system, stable-boson-fermion nuclear structure.

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Boson Fermion Nuclei Stellar Nucleosynthesis: Monograph #7

Stellar nucleosynthesis is generally described as the process by which nuclei are combined through fusion to create larger nuclei by the specific addition of nucleons, leading to a stable nucleus of a higher positive charge (Z) or nucleon number (A), or both. By contrast, the boson fermion nucleus (BFN) attributes the creation of nuclei to highly chaotic processes within a star. Under high pressure and temperature within the star, and given a certain probability of overcoming coulomb barriers, nucleons and first-period nuclear components agglomerate in a manner that rarely results in a stable nuclear structure. On a random basis, proto-nuclei are conveyed out of the star’s central agglomeration zone in an upwelling flow from within the star. As these proto-nuclei evolve to their lowest energy state, they shed nucleons and undergo radioactive decay, emerging as a stable BFN structure.

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Boson Fermion Nuclei Monograph Series: Monograph #6

Monographs 1 through 5 show that nuclei in the second and third periods of the periodic table of elements are made of components that are nuclei in the first period. This leads to descriptions of nuclear structures throughout the periodic table that account for many of the observed properties of nuclei and atoms. The boson fermion nucleus is significant in that it offers a unified explanation for many observables and predicts the creation of materials with extraordinary properties.

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A New Approach for Calculating the Alpha-Decay Half-Life for the Heavy and Super-heavy Elements and an Exact A Priori Result for Beyllium-8

A new general method for calculating the alpha decay half-life is presented. The method predicts an a priori exact value for the beryllium-8 half-life. Beryllium-8 is an exception to the current alpha decay theory captured in the Geiger-Nuttal law. The new method predicts the beryllium-8 alpha half-life using only constants and measured isotopic mass. The method also reliably predicts all the heavier isotope alpha decay half-lives consistent with the Geiger-Nuttal law. With respect to current theory, the inability of the Geiger-Nuttal Law to predict the alpha-decay half-life in the case of beryllium-8 has led to consideration of other decay mechanisms for this isotope, such as fission for example. One result is that given the consistency of the new method presented here for all isotopes including an exact a priori result for beryllium-8, the evidence strongly suggests that the beryllium-8 decay is in fact an alpha decay. A second result is that the method definitively demonstrates that the entire rest mass of the two helium-4 electrons is converted to energy in the decay process and this energy becomes part of the emitted alpha particle kinetic energy.

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Advancing Fissile Materials Production Modeling with Adaptive Computing Environment and Simulations (ACES)

The Department of Energy’s National Nuclear Security Administration (DOE/NNSA) provides advanced capabilities to simulate the uranium enrichment process to support international negotiations on the peaceful use of nuclear energy. Uranium isotope separation centrifuges connected in a cascade configuration can produce the low-enriched uranium needed for nuclear power. However, those same centrifuges connected in a different configuration can also produce highly enriched uranium for nuclear weapons. Having the capability to assess cascade operations and identify nefarious activities promotes the peaceful uses of nuclear energy while restricting nuclear weapons proliferation. DNN R&D's Nonproliferation Stewardship Program Adaptive Computing Environment and Simulations (ACES) project is creating a modern, sustainable ecosystem of physics-based models and data-analytics tools that enables analysts to model uranium enrichment systems, simulate operational scenarios, and apply various policy options to explore potential outcomes.

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Xenon Abatement Simulations to Support the KAERI Medical Isotope Facility

To maintain and improve the verification regime that is outlined by the Preparatory Commission of the Comprehensive Nuclear Test-Ban Treaty there is a need to understand and reduce the radioxenon releases from medical isotope production facilities. In support of this objective Pacific Northwest National Laboratory (PNNL) was tasked with, modeling and evaluate the abatement process and delay bed designs for the medical isotope production facility under construction by the Korea Atomic Energy Research Institute (KAERI). This report includes this analysis and provides PNNL proposed modifications to the KAERI adsorption bed design.

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Recovery and Recycle of Irradiated Low-Enriched Uranium from the Production of 99 Mo

Technetium-99m ( 99m Tc), the daughter (decay product) of molybdenum-99 ( 99 Mo), is the most commonly used medical radioisotope in the world. 99 Mo is produced primarily from the fissioning of 235 U. A potential future producer, Eden Radioisotopes, is planning to irradiate low-enriched-uranium metal-foil targets for production of 99 Mo. Their plan is to recover, purify, and recycle the irradiated LEU in a new set of targets inside their facility. This study assesses processes to (1) purify and recycle uranium following 99 Mo recovery and (2) convert the uranium to metal for subsequent foil production and target fabrication. A UREX (uranium recovery by extraction) liquid–liquid extraction flowsheet that utilizes centrifugal contactors was developed using the Argonne model for universal solvent extraction (AMUSE) to recover and purify the uranium. The calculated flowsheet predicted high decontamination from Pu and most fission products and >99.99% recovery of uranium. Suggestions for conversion of the UREX U-product (uranyl nitrate in dilute nitric acid) to U metal were provided based on literature studies and earlier laboratory studies performed at Argonne National Laboratory.

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Irradiation of 20L LEU Uranyl Sulfate Solution for Production of Mo-99

Argonne National Laboratory, with support from the National Nuclear Security Administration’s Office of Material Management and Minimization, is assisting SHINE Medical Technologies in the development of accelerator-driven production of 99 Mo using low-enriched uranium (LEU). Technetium-99m ( 99m Tc), a daughter of 99 Mo, is a workhorse of nuclear medicine, used in approximately 40,000 medical testing procedures each day just in the U.S.

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