Index Catalog // ScholarsArchive@OSU

Purification of cyclotron-produced 89Zr for its use in diagnostic radiopharmaceutical labeling

Creator:: Knaus, Clinton W.
Abstract:: Production of 89Zr serves as a crucial preliminary step for exploring Zr-chelates, determining their stability constants, and advancing radiolabeling methodologies for monoclonal antibody based theranostics. 89Zr is typically produced by the irradiation of natural yttrium targets, a process extensively documented in scientific literature. Two primary methods are employed: the 89Y(p,n)89Zr...
Resource Type:: Capstone Project
Full Text:: unexpected life changes compelled me to walk away. Thank you to my Dr. Meier and Dr. Yang for being

Comparison of Attila SN Particle Transport Code with MCNP in the Analysis of Small Modular Reactor Shielding

Creator:: Rose, Charlotte
Abstract:: Of great importance in the design of a nuclear power plant is the evaluation of shielding from the ionizing radiation produced in the core of the nuclear reactor. This requires simulation software to predict the dose rates in the areas of interest. Comparing the simulation of the same modeled system...
Resource Type:: Masters Thesis

Investigation of Drag Coefficient and Virtual Mass Coefficient on Rising Ellipsoidal Bubbles

Creator:: Dueñas, Alexander M.
Abstract:: Accurately describing drag and virtual mass forces in two-phase flows is crucial for high fidelity modeling of nuclear thermal hydraulic safety systems. This study compares existing drag coefficient correlations commonly used in computational fluid dynamics (CFD) applications for air bubbles to experimental data collected for ellipsoidal air bubbles of varying...
Resource Type:: Masters Thesis

Investigation Into the Use of a Lead Slowing Down Spectrometer for Neutron Cross Section Analysis

Creator:: Keppen, Jackson D.
Abstract:: A lead slowing-down spectrometer (LSDS) was modeled in the hopes of beginning a nuclear data development campaign at Oregon State University. An LSDS can be used for neutron interrogation techniques, such as determining isotopic inventory of a sample of unknown components or determining the cross section of a sample of...
Resource Type:: Honors College Thesis
Full Text:: State’s School of Nuclear Science and Engineering Haori Yang, Committee Member, representing Oregon

Characterization of Radionuclide Resuspension via Aeolian Processes at the Ambrosia Lake West Mill Facility

Creator:: Adriatico, Vanessa L.
Abstract:: The Ambrosia Lake West Site is a former uranium recovery facility located north of Grants, New Mexico. It currently serves as a uranium mill tailings site undergoing reclamation and decommissioning. High velocity winds are common in the area, causing soil erosion via aeolian processes. Strong winds may carry soil for...
Resource Type:: Masters Thesis

Neutron Flux-Energy Spectral Characterization of a Deuterium-Tritium Neutron Generator at Oregon State University

Creator:: Eastman, Abigail L.
Abstract:: The neutron flux-energy spectral characterization of a Thermo Fisher MP320 deuterium-tritium neutron generator was performed for two shielding configurations, one with substantial moderator between the source and the sample and one without such moderator. The STAYSL PNNL spectral adjustment code was utilized in conjunction with MCNP modelled reference spectra and...
Resource Type:: Masters Thesis

Dosimetry Model for Alpha Emitters in a Radioactive Skin Patch for Treatment of Early-Stage Nonmelanoma Skin Cancers

Creator:: Squillante, Joyce
Abstract:: Nonmelanoma skin cancer (NMSC) is the most common malignancy in Caucasian populations. One existing treatment modality for NMSCs is external radiotherapy delivered to the skin cancer tumor by a beta-emitter-containing radioactive skin patch. Alpha emitters, with their higher linear energy transfer than beta particles and shorter range in tissue, make...
Resource Type:: Masters Thesis

Development of a High-Energy Neutron Sniffer and Subsequence Dose Quantification for High-Energy Particle Accelerator Shielding Surveys

Creator:: Overbay, Lauren A.
Abstract:: The objective of this research is to design a portable neutron detector that is lightweight and responds to neutrons with energies of 20 MeV and greater. The instrument will be used as a ‘sniffer’ probe for identifying shielding weaknesses at high-energy particle accelerators and be paired with a plastic scintillator...
Resource Type:: Masters Thesis

Dosimetric Evaluation of Nasal Cavity Basal Cell Layer during Radiotracer Administration

Creator:: Flora, Rigel
Abstract:: New delivery methods for radiotracers are constantly being proposed. Two key properties of the delivery method must be analyzed: dose to patient and effectiveness of delivery. In this work, the localized skin dose for intranasal administration of 18F was determined utilizing MCNP code. An anatomically accurate nasal cavity was constructed...
Resource Type:: Masters Thesis

Understanding the Application and Benefits of Learning-based Methods in Nuclear Science and Engineering

Creator:: Gómez Fernández, Mario Enrique
Abstract:: Known as the fourth industrial revolution, digitization is an ongoing trend in all ﬁelds, in which various industries are integrating information technologies to support and improve their businesses. Nuclear technology industries have also increased their interest in data-driven methods by leveraging the potential of pattern recognition to identify anomalies and...
Resource Type:: Dissertation
Full Text:: Akira Tokuhiro Kent Welter Weng-Keen Wong Haori Yang Nuclear Science and Engineering, Oregon State

ScholarsArchive@OSU

Purification of cyclotron-produced 89Zr for its use in diagnostic radiopharmaceutical labeling

Comparison of Attila SN Particle Transport Code with MCNP in the Analysis of Small Modular Reactor Shielding

Investigation of Drag Coefficient and Virtual Mass Coefficient on Rising Ellipsoidal Bubbles

Investigation Into the Use of a Lead Slowing Down Spectrometer for Neutron Cross Section Analysis

Characterization of Radionuclide Resuspension via Aeolian Processes at the Ambrosia Lake West Mill Facility

Neutron Flux-Energy Spectral Characterization of a Deuterium-Tritium Neutron Generator at Oregon State University

Dosimetry Model for Alpha Emitters in a Radioactive Skin Patch for Treatment of Early-Stage Nonmelanoma Skin Cancers

Development of a High-Energy Neutron Sniffer and Subsequence Dose Quantification for High-Energy Particle Accelerator Shielding Surveys

Dosimetric Evaluation of Nasal Cavity Basal Cell Layer during Radiotracer Administration

Understanding the Application and Benefits of Learning-based Methods in Nuclear Science and Engineering

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