Title

Radiation Transport Modeling of Gamma Ray Tomography System

Presenter Information

Reagan Dugan

Department

Nuclear Engineering and Radiation Science

Major

Physics

Research Advisor

Graham, Joseph

Advisor's Department

Nuclear Engineering and Radiation Science

Abstract

New accident-tolerant nuclear fuel designs that incorporate advanced safety features and economy are being designed to advance the next generation of nuclear reactors. Experiments are being conducted at nuclear test reactors to determine the overall reliability and performance of the accident-tolerant fuel at both normal operating conditions and beyond-design conditions. This project was tasked with modeling a high-resolution submersible gamma computed tomography (CT) system that utilizes a strong gamma ray source and an array of radiation detectors to measure the transmission of gamma rays from the source through the fuel. The transport of radiation in the tomography system was modeled in the Monte Carlo N-Particle (MCNP) software, which was used to evaluate system performance at various design parameters.

Biography

Reagan Dugan is a former Nuclear Engineering student and current Physics student. He graduated from David H. Hickman high school in 2015 and is currently a junior at Missouri S&T. Reagan has spent his undergraduate time focusing on medical applications of nuclear technology, such as medical imaging and radiation therapy. Upon graduation in the spring of 2019, he plans to begin a graduate program in medical physics and hopes to eventually work in a clinical setting in the radiation oncology unit of a hospital.

Research Category

Engineering

Presentation Type

Poster Presentation

Document Type

Poster

Location

Upper Atrium

Presentation Date

17 Apr 2018, 1:00 pm - 4:00 pm

Comments

Joint project with: Meelap Coday

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Apr 17th, 1:00 PM Apr 17th, 4:00 PM

Radiation Transport Modeling of Gamma Ray Tomography System

Upper Atrium

New accident-tolerant nuclear fuel designs that incorporate advanced safety features and economy are being designed to advance the next generation of nuclear reactors. Experiments are being conducted at nuclear test reactors to determine the overall reliability and performance of the accident-tolerant fuel at both normal operating conditions and beyond-design conditions. This project was tasked with modeling a high-resolution submersible gamma computed tomography (CT) system that utilizes a strong gamma ray source and an array of radiation detectors to measure the transmission of gamma rays from the source through the fuel. The transport of radiation in the tomography system was modeled in the Monte Carlo N-Particle (MCNP) software, which was used to evaluate system performance at various design parameters.