Showing 59 results for Author: Kristian G. Myhre
Jun, 2024
Journal
The use of heavy actinide targets, including 243Am, 240,242,244Pu, 245,248Cm, 249Bk, and 249Cf, irradiated by intense heavy ion beams of 48Ca has resulted in a significant expansion of the periodic table since 2000, including the discovery of five new heaviest elements and more than 50 new isotopes. These actinide materials can only be produced by intense neutron irradiati…
Dec, 2023
Journal
Molten salt reactors (MSRs) are being investigated as a possible source of 99Mo for medical uses. This paper describes computational modeling being performed to determine the feasibility for use of several MSR concepts in 99Mo production: the Molten Salt Breeder Reactor (MSBR), the Molten Salt Demonstration Reactor (MSDR), and the Molten Salt Reactor Experiment (MSRE). Thi…
Nov, 2023
Conference Paper
Nov, 2023
Journal
Attenuation-based neutron computed tomography (CT) has been used to non-destructively characterize the uncoated tristructural-isotropic (TRISO) nuclear fuel kernels in this work. Particularly, the effect of two different types of carbon blacks (Raven 3500 and Mogul L) on the internal gelation process of UO3-C kernels has been investigated. With 3D reconstructed kernel volu…
Nov, 2023
Journal
Laser-induced breakdown spectroscopy (LIBS) is a versatile technique for compositional analysis for solids, liquids, or gasses. LIBS is an asset for the quantitative or qualitative analysis of resource limited materials like actinides and rare earths because it is quasi-nondestructive. Two Eu2O3 pellets were synthesized to be a test and validation set, respectively. Spectr…
Nov, 2023
Journal
Technitium-99m (99mTc), a widely used radioisotope, is used in tens of millions of medical diagnostic procedures annually. However, it is hard to store and must be immediately used upon production due to its short half-life (i.e., 6 h); thus, it is currently produced from 99Mo, which itself is a result of 235U fission. The majority of 99Mo supplies to U.S. patients are cur…
Nov, 2023
Journal
The Plutonium-238 Supply Program at Oak Ridge National Laboratory has developed the capability to inform process decisions during full-scale 238Pu anion exchange column runs using multivariate chemometrics and visible-near infrared (Vis-NIR) absorption spectroscopy. Multivariate analytical methods provided a suitable option for real-time analysis of complex neptunium (Np)…
Nov, 2023
Journal
Current methods for quantitative dissolution of solid PuO2 involve lengthy dissolution times. The adaptation of mediated electrochemical oxidation, which uses an electrochemically produced oxidizing agent to catalyze dissolution, has been explored for radiochemical analysis scale dissolutions of PuO2. The effects of temperature, electrode material, and electrocatalyst on t…