Index Catalog // ScholarsArchive@OSU

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

Creator:: Lilley, Benjamin C.
Abstract:: Material testing experiments are needed to enable the next generation of nuclear fission reactors. Concluding in 2009, the Boosted Fast Flux Loop (BFFL) project was devised as a way to test fast reactor materials and fuels in the Advanced Test Reactor (ATR), however the experiment location it used is now...
Resource Type:: Masters Thesis
Full Text:: (2014). [4] G. R. LONGHURST, D. P. GUILLEN, J. R. PARRY, D. L. PORTER, and B. W. WALLACE, “Boosted

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

Creator:: Kumar, Ravi
Abstract:: In this thesis, we expand the scope of a previously introduced Artificial Neural Network (ANN) method to solve the slab-geometry discrete ordinates (S$_N$) neutron transport equations. Specifically, we extend the method to energy-dependent (multi-group) fixed source problems involving heterogeneous media and more general boundary conditions - vacuum and incident flux...
Resource Type:: Masters Thesis
Full Text:: angular neutron density, is a function of radial distance r, direction Ω, and energy E. N can be related

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

Creator:: Blake, Grant C.
Abstract:: The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors...
Resource Type:: Masters Thesis
Full Text:: , Dr. Cadell, Rachel, and Ben Blake for proof-reading. Dr. Woods, Dr. Reese, Dr. Cadell, and Dr

Comparison of total dose to individuals from temperate and arid environments

Creator:: Elmore, Brockway F., II
Abstract:: This paper analyzes the decision-making process utilized in temperate environments for building nuclear facilities and whether it was going to be applicable to nuclear facilities built in arid environments. To answer this question, the total dose to individuals from arid and temperate environments were compared using RESRAD-OFFSITE and changing the...
Resource Type:: Masters Thesis

Nanoscale Instrumented Indentation Testing with the Current Capabilities of MOOSE and Marmot

Creator:: VandenBroeder, Gavin T.
Abstract:: Nanoscale Instrumented Indentation Testing (IIT) is a material characterization technique that is used to determine mechanical properties. The size effects present at this scale make it difficult to expand findings to a bulk scale. Modeling can be used to bridge this gap and better understand nanoscale IIT and the size...
Resource Type:: Masters Thesis
Full Text:: compared to that of the 101st, and the R squared between them is plotted, this is done for 101st to 151st

Developing Software Tools to Characterize Electrochemical Loss Scenarios via Gamma Detection for Various Measurement Points, Source Geometries, and Process Times

Creator:: Harris, Noah C.
Abstract:: Faithful modeling of the expected gamma signals inside an electrochemical facility at various key measurement points is important for understanding what detection limits are available for the next generation of safeguards technologies. Gamma Detector Response and Analysis Software (GADRAS) and the Separation Safeguards Performance Model (SSPM) were used to build...
Resource Type:: Masters Thesis

Silicon Photomultiplier Modeling of CsI(Tl) with Front End Electronics using a Monte Carlo Model

Creator:: McGee, Kacey D.
Abstract:: Silicon photomultipliers (SiPM) have become increasingly popular in radiation detection design due to smaller profiles, lower operating voltage, and magnetic insensitivity. However, there are nonlinear effects that make modeling SiPM challenging. This study looks at using a Monte Carlo approach to modeling the output of an SiPM and front end...
Resource Type:: Masters Thesis
Full Text:: like to thank Dr. Abi Farsoni, Steven Czyz, Harish Gadey, and Mitch Mannino for their patience, time

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Creator:: Tamashiro, Aaron S.
Abstract:: During the past few decades, the U.S. Department of Energy (DOE) has made significant investments to improve nuclear data libraries, as the quality of this data impacts nearly all analyses of nuclear systems. Nuclear fission product yields are one component of these libraries, and are important for the analysis of...
Resource Type:: Masters Thesis
Full Text:: Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2 METHODS 10 2.1 R - Branching Ratio

Eye Lens Doses from Oblique Sources

Creator:: Trakowski, Ian M.
Abstract:: Since the International Commission on Radiation Protection (ICRP) recommended a revision to the eye lens dose limits in ICRP Publication 118 (Stewart, 2012) the radiation protection community has conducted many new studies related to eye dosimetry. The recommended reduction of eye lens dose limits may result in the reduction of...
Resource Type:: Masters Thesis

Human Eye Dosimetry: Air Gap Analysis by Shield Placement and Photon Energy

Creator:: Herrera, Joshua P.
Abstract:: When the ICRP updated their recommended limits for eye dose, they ignited a renewed interest in eye dosimetry. Especially, how the updated eye dose estimates affect current regulations and what that would mean to a radiation worker. Radiation workers are commonly required to wear leaded eyeglasses to reduce their dose...
Resource Type:: Masters Thesis
Full Text:: .............................................................. 63 Appendix Figures R: 1.0 MeV Photon Energy to Dose Curve

ScholarsArchive@OSU

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

Comparison of total dose to individuals from temperate and arid environments

Nanoscale Instrumented Indentation Testing with the Current Capabilities of MOOSE and Marmot

Developing Software Tools to Characterize Electrochemical Loss Scenarios via Gamma Detection for Various Measurement Points, Source Geometries, and Process Times

Silicon Photomultiplier Modeling of CsI(Tl) with Front End Electronics using a Monte Carlo Model

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Eye Lens Doses from Oblique Sources

Human Eye Dosimetry: Air Gap Analysis by Shield Placement and Photon Energy

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