Fission product yields (FPYs) are used for a wide range of applications including nuclear fission theory, nuclear reactor design, reactor antineutrino anomaly, stellar nucleosynthesis, and nuclear forensics. These applications rely on FPYs that were last evaluated in 1993, which included measurements from all over the world up until 1993. In...
The pulsed sphere benchmark problems are a set of physical experiments that have been used to verify Monte Carlo codes and evaluate nuclear data. All Monte Carlo codes rely on benchmark experiments that test the features of the code to verify that the simulations are producing realistic results. In the...
In this dissertation we consider two application specific flow and transport models in porous media at multiple scales: 1) methane gas transport models for hydrate formation and dissociation in the subsurface under two-phase conditions, and 2) coupled flow and biomass-nutrient model for biofilm growth in complex geometries with biofilm, and...
The International Atomic Energy Agency (IAEA) is responsible for verifying the mass of elemental uranium in various forms (powders, pellets, scrap) as part of safeguards inspections at nuclear fuel fabrication facilities in support of the nuclear non-proliferation treaty. Current methods require in-field dissolution chemistry, which is time consuming and imposes...
The Transient Reactor Test facility (TREAT) at Idaho National Laboratory (INL) is a unique reactor capable of stressing test fuel during a power pulse transient. TREAT fuel is composed of high enriched uranium (HEU) heterogeneous fuel; microscopic UO₂ fuel grains with an average radius of 10 μm are randomly distributed...
Mathematical modeling plays a pivotal role in understanding the mechanism of radiation-induced cellular effects, and also in quantifying the radiation risk to the cell. However, there are still compelling challenges facing the conventional modeling in radiobiology, such as lacking a generalized theory structure of quantifying target effect and non-target effect...
The research presented in this dissertation focuses on the model generation and modeling processes of student teams that participate in capstone, undergraduate engineering physical and virtual laboratory projects. The Heat Exchange Laboratory Project, the Ion Exchange Laboratory Project, and the Virtual Chemical Vapor Deposition (CVD) Laboratory Project provide the context...
The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...