A wide selection of deterministic and stochastic methods have been developed to conduct nuclear reactor criticality calculations and to improve the efficiency of these methods, a branch of neutronics method research focuses on the acceleration of source convergence process which…
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The advancement of nuclear technology has resulted in new and unique thermal reactor designs beyond the typical light water reactors which currently dominate the reactor fleet. The verification and validation advanced thermal reactor performance require an accurate understanding…
A critical challenge to the continued use of engineering structures as they are asked to perform longer than their design life is the prediction of an initiating crack and the prevention of damage, estimation of remaining useful life, schedule maintenance and to reduce costly do…
Today, probabilistic risk assessments (PRAs) at multi-unit nuclear power plants consider risk from each unit separately and do not formally consider interactions between the units. These interactions make the operation of multiple units dependent on each other and should be acco…
The aim of this study is to identify environmental effects on tree-ring chemistry. It is known that industrial pollution, volcanic eruptions, dust storms, acid rain and similar events can cause substantial changes in soil chemistry. Establishing whether a particular group of tre…
Rod bundle is a typical constitutive element of a very wide range of nuclear reactor designs. This thesis describes the investigation of such geometry with wall-resolved Large Eddy Simulation (LES). In order to alleviate the mesh constraint, imposed by the near wall resolution, …
Dendrochemistry is a term used to describe the compositional analysis of tree-rings and its application to biomonitoring of the tree's environment. The central hypothesis of this study is that the concentrations of silver and gold in tree-rings in the Mediterranean region record…
The TRIGA Mark F reactor at the Armed Forces Radiobiology Research Institute in Bethesda Maryland is a 1 megawatt steady state reactor which can also be operated in pulse mode at a power of up to 2500 megawatts. It is characterized by a moveable core and two large exposure rooms…
Problems which originate in early development stages can have a lasting influence on the reliability, safety, and cost of a software system. The requirements document, which is usually available at the requirements analysis stage, must be correct, unambiguous, and complete if th…
Two MCNP models (detailed and approximated) of the University of Maryland Training Reactor were created. The detailed model attempted to simulate the reactor according to engineering specifications while the simplified model eliminated all structural materials above and below th…
In this research study, MATLAB PDE Toolbox is investigated for modeling a two-dimensional (2-D) and three-dimensional (3-D) pressurized water reactor (PWR) core. MATLAB PDE Toolbox is a partial differential equation (PDE) solver for finite element method (FEM) analysis. The PDE …
Nuclear reprocessing is a technique used to recover uranium and plutonium from used nuclear fuel for the purpose of manufacturing new fuel or atomic weapons and involves the production of radioactive wastes. Nuclear reprocessing overall can reduce the volume of radioactive waste…
Scientists and engineers have been working for many years to develop accurate approaches to analyzing nuclear power reactors using computer codes that closely model the behavior of neutrons in a reactor core. The Monte Carlo simulation method is capable of treating complex geome…
This dissertation presents a study on the structural integrity of spent nuclear fuel (SNF) transportation casks, considering hydride-related material degradation of pressurized water reactor (PWR) fuel rod cladding after long-term dry storage of up to 300 years. The thin-walled …
Vacuum drying of nuclear fuel canisters may cause the temperature of fuel assemblies to considerably increase due to the effect of gas rarefaction at low pressures. This effect may induce a temperature-jump at the gas-solid interfaces. It is important to predict the temperature-…
Despite the tremendous growth of computational resources in recent years, the "curse of dimensionality" associated with the canonical evolutionary partial differential equations in nuclear reactor engineering and thermal-hydraulics such as the direct solution to non-linear Navie…
This research conducted thermal-hydraulic analysis on a thermal shield of the National Bureau of Standards Reactor (NBSR) using computational fluid dynamics (CFD) techniques with ANSYS 19.2. The NBSR thermal shield is a hollow, cylindrical water-cooled lead-steel structure surro…
Many accidents are attributed to human errors. Abundant evidences could be found in major accidents in petro-chemical, nuclear, aviation, and other industries. In the nuclear power industry, safe operation heavily relies on the operators' interaction with plant systems. For exam…