Title

Radiation Transport Modeling of Gamma Ray Tomography System

Presenter Information

Meelap Coday

Department

Nuclear Engineering and Radiation Science

Major

Nuclear Engineering

Research Advisor

Graham, Joseph

Advisor's Department

Nuclear Engineering and Radiation Science

Funding Source

Opportunities for Undergraduate Research Experiences (OURE)

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

Meelap Coday is a senior in Nuclear Engineering at Missouri University of Science and Technology. He will be graduating in May of 2018 with a B.S. in Nuclear Engineering with a Minor in Mathematics. He is a member of the Sigma Chi Fraternity and was also the vice president of the American Nuclear Society (ANS).

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 Reagan Dugan

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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.