An important method in validating neutron cross sections is the execution of critical experiments. In these experiments, changes in the neutron multiplication factor, k, are observed as a function of perturbations in cross sections. Due to the risk of working with radioactive materials, it is important for the design to be analyzed for safety and feasibility. This includes considering factors such as the thermal properties of the materials, their weight, structural integrity of the system, and the feasibility of manufacturing and assembling the parts.

This project entails the design of a purification system for molten sodium coolant in a sodium-cooled fast reactor (SFR). The AFR-100 design from Argonne National Laboratory was used as the basis for the system. The purification system is comprised of a combination of both hot and cold traps placed in the core assembly and primary loop of the reactor. The cold trap design was chosen from a previously-used cold trap in a sodium-cooled reactor. The decision matrix is based on design parameters chosen based on the reactor, with an emphasis on trap efficiency.

The goal of this project is to generate an implementable design for a nuclear-powered cargo ship through the consolidation of preexisting ships and nuclear reactors. After a considerable amount of work, the group has come to the conclusion that a Maersk Triple-E class cargo ship would be a suitable vessel that could be easily powered by two 60-MW NuScale power modules. These two reactors will power a ship that, when fully loaded, can carry up to 18000 containers.

The goal of this project is to develop the method and data to create a software which will compute the dose to a patient receiving a routine chest x-ray scan. The team will compute dose to patient through the use of MCNP which can accurately calculate energy deposition in a given area with below 5% uncertainty. From energy deposition, dose to a given organ can be calculated by utilizing conversion factors and normalizing to values measured with a detector.

The objective of this senior design project is reviewing the case of the Fukushima-Daiichi nuclear power plant accident through online resources such as news, official websites and published accident reports. By examining the structure of the power plant, the detailed accident impact on it as well as failed system components, any causes and preventative measures will be determined.