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Tertiary Safety System For Nuclear Spent Fuel Pool, Jonathan Farmer, Amanda Bachmann, Taylor Adams, Eissa Altalahlah, Trina Garrett, Jillian Newmyer, Drew Shayotovich 2019 University of Tennessee, Knoxville

Tertiary Safety System For Nuclear Spent Fuel Pool, Jonathan Farmer, Amanda Bachmann, Taylor Adams, Eissa Altalahlah, Trina Garrett, Jillian Newmyer, Drew Shayotovich

Chancellor’s Honors Program Projects

No abstract provided.


Manufacture Of Dual Sided Microstructured Semiconductor Neutron Detectors, Jared Medina 2019 Kansas State University Libraries

Manufacture Of Dual Sided Microstructured Semiconductor Neutron Detectors, Jared Medina

Kansas State University Undergraduate Research Conference

The world is in need of a new way to detect neutrons. The best current detectors rely on 3He, which is in short supply. The 3He detectors are extremely expensive. The goal of this project is to produce inexpensive and robust detectors that do not rely on 3He. Instead of using gas, the Dual Sided Microstructured Neutron Detectors (DS-MSNDs) are made from a semiconductor material. The DS-MSNDs have been simulated to have up to 70% efficiency, which is comparable to the 3He detectors efficiency of about 80%. The DS-MSNDs have micro-trenches that are back filled with ...


Measurement And Analysis Of The Extreme Physical Shock Environment Experienced By Crane-Mounted Radiation Detection Systems, Matthew Boyd, Jennifer Erchinger, Craig M. Marianno, Gene Kallenbach 2019 Texas A & M University - College Station

Measurement And Analysis Of The Extreme Physical Shock Environment Experienced By Crane-Mounted Radiation Detection Systems, Matthew Boyd, Jennifer Erchinger, Craig M. Marianno, Gene Kallenbach

International Journal of Nuclear Security

At ports of entry, radiation detectors could be mounted on container gantry crane spreaders to monitor cargo containers entering and leaving the country. These detectors would have to withstand the extreme physical conditions experienced by these spreaders during normal operations. Physical shock data from the gable ends of a spreader were recorded during the loading and unloading of a cargo ship by two hard mounted PCB Piezotronics model 340A50 accelerometers and two Lansmont SAVER 9X30 units (with padding). The majority of large shocks were observed in the vertical direction. The Lansmont units recorded mean shocks of 22.215 ± 1.174 ...


Compositional Analysis Of Cerium And Cesium In Rapid Setting Cement As An Immobilization Agent For Nuclear Waste, RIYADH M. MOTNY 2019 Virginia Commonwealth University

Compositional Analysis Of Cerium And Cesium In Rapid Setting Cement As An Immobilization Agent For Nuclear Waste, Riyadh M. Motny

Theses and Dissertations

A feasibility of rapid setting cement (RSC) as an agent of immobilization for certain elements such as fission products or radioactive materials was explored. Cerium (Ce) and cesium (Cs) have been selected as a surrogate for U and/or Pu and fission products, respectively, in this study in three phases. In Phase I, RSC was evaluated for physical properties (e.g., porosity, density, pH values, etc.) using two groups methods—the cement powder at different concentrations of Ce (2 – 10 wt%) with deionized water (DIW) and artificial seawater (ASW). The results showed that the final setting time and compressive strength ...


Call For Abstracts - Resrb 2019, July 8-9, Wrocław, Poland, Wojciech M. Budzianowski 2018 Wojciech Budzianowski Consulting Services

Call For Abstracts - Resrb 2019, July 8-9, Wrocław, Poland, Wojciech M. Budzianowski

Wojciech Budzianowski

No abstract provided.


Radiolabeled Nanohydroxyapatite As A Platform For The Development Of New Pet Imaging Agents, Stacy Lee Queern 2018 Washington University in St. Louis

Radiolabeled Nanohydroxyapatite As A Platform For The Development Of New Pet Imaging Agents, Stacy Lee Queern

Arts & Sciences Electronic Theses and Dissertations

Positron emission tomography (PET) imaging utilizes drugs labeled with positron emitters to target and evaluate different biological processes occurring in the body. Tailoring medicine to the individual allows for higher quality of care with better diagnosis and treatment and is a key purpose for advancing research into developing new platforms for PET imaging agents. A PET nuclide of high interest for the development of these agents is 89Zr. This can be attributed to the long half-life of 3.27 days and low positron energy of 89Zr.

In this work, we developed a production method for 89Zr using Y sputtered coins ...


Development Of The University Of New Mexico Spectrometer For High-Resolution Fission Product Yield Data, Richard Emery Blakeley 2018 University of New Mexico - Main Campus

Development Of The University Of New Mexico Spectrometer For High-Resolution Fission Product Yield Data, Richard Emery Blakeley

Nuclear Engineering ETDs

Well-defined fission product yield data has been of increasing interest in various applications within the nuclear industry. With this need in mind, a fission fragment mass spectroscopy system was designed and developed at the University of New Mexico in collaboration with the Los Alamos National Laboratories with a stated goal of attaining a mass resolution of ≤ 1 % (FWHM/centroid) for light fragments and near 1 % for heavy fragments. The mass spectrometer utilized in this work consists of a transmission time-of-flight detection system to measure fission product velocity and an axial ionization chamber to measure the fission product energy, with measurements ...


Corrosion Dynamics Of Carbon Steel In Used Fuel Container Environments, Dan Guo 2018 The University of Western Ontario

Corrosion Dynamics Of Carbon Steel In Used Fuel Container Environments, Dan Guo

Electronic Thesis and Dissertation Repository

The current Canadian used nuclear fuel container (UFC) design uses a pressure‑grade carbon steel (CS) vessel with its outer surface coated with a thin layer of copper. One concern regarding the structural integrity of the UFC design is the potential internal corrosion of the CS vessel. Moisture trapped inside a UFC could condense within the gap between the hemispherical head and the cylindrical body of the vessel. The internal UFC environment will be exposed to a continuous flux of ionizing radiation arising from the decay of radionuclides trapped in the used UO2 fuel matrix.

This thesis research project ...


Exploration Of Radiation Damage Mechanism In Mems Devices., Pranoy Deb Shuvra 2018 University of Louisville

Exploration Of Radiation Damage Mechanism In Mems Devices., Pranoy Deb Shuvra

Electronic Theses and Dissertations

We explored UV, X-ray and proton radiation damage mechanisms in MEMS resonators. T-shaped MEMS resonators of different dimensions were used to investigate the effect of radiation. Radiation damage is observed in the form of resistance and resonance frequency shift of the device. The resistance change indicates a change in free carrier concentration and mobility, while the resonance frequency change indicates a change in mass and/or elastic constant. For 255nm UV radiation, we observed a persistent photoconductivity that lasts for about 60 hours after radiation is turned off. The resonance frequency also decreases 40-90 ppm during irradiation and slowly recovers ...


Investigating The Electrodeposition Of Plutonium And Curium For Safeguarding The Electrorefiner, Chantell L. Murphy 2018 University of New Mexico

Investigating The Electrodeposition Of Plutonium And Curium For Safeguarding The Electrorefiner, Chantell L. Murphy

Nuclear Engineering ETDs

This research investigated the electrochemical deposition behavior of plutonium (Pu) and curium (Cm) for safeguarding the electrorefiner (ER) in a pyroprocessing facility. The main goal of this investigation was to evaluate the feasibility of using a safeguards concept called the neutron balance method to account for Pu in the ER. The neutron balance method relies on a known Pu/Cm ratio and measures neutrons from Cm-244 coming into and leaving a unit operation to track Pu. The application of the neutron balance approach for pyroprocessing facilities requires that Pu and Cm remain together in all extraction, product recovery, and waste ...


Comparison Of Steady And Transient Flow Boiling Critical Heat Flux (Chf) For Fecral Accident Tolerant Fuel Cladding Alloy, Zircaloy, And Inconel, Soon Kyu Lee 2018 University of New Mexico - Main Campus

Comparison Of Steady And Transient Flow Boiling Critical Heat Flux (Chf) For Fecral Accident Tolerant Fuel Cladding Alloy, Zircaloy, And Inconel, Soon Kyu Lee

Shared Knowledge Conference

The nuclear reactor design focuses on building a system that is robust and reliable, is efficient and economical, and do not run into undesirable transient accident scenarios. The nuclear reactor safety focuses on ensuring the system operation under the safety margins and requirements provided by the regulatory agencies. Following the Fukushima nuclear reactor accident, the US Department of Energy Office of Nuclear Energy (DOE-NE) Advanced Fuels Campaign (AFC) is working to develop fuel and cladding candidates with potentially enhanced accident tolerance: ‘Advanced Tolerant Fuel’ (ATF). As a part of the AFC, this research focuses on gaining mechanistic understanding of the ...


Radiation Transport In Stochastic Media, Corey Skinner 2018 University of New Mexico

Radiation Transport In Stochastic Media, Corey Skinner

Shared Knowledge Conference

The need to investigate numerical methods for the transport of radiation (thermal photons, light, neutrons, gammas) in random mixtures of immiscible materials arises in numerous applications, including inertial confinement fusion, turbid media (e.g., skin tissue), stellar atmospheres, clouds, and pebble bed nuclear reactors. Stochastic geometry techniques enable rendering of realizations of such random media and deterministic finite difference/finite element as well as Monte Carlo techniques are used to numerically simulate radiation transport on a large ensemble of realizations. The results are then averaged to obtain statistical moments of the radiation intensity, in particular the mean and variance, to ...


Use Of High Fidelity Fission Models In Criticality Calculations, Daniel H. Timmons 2018 University of New Mexico - Main Campus

Use Of High Fidelity Fission Models In Criticality Calculations, Daniel H. Timmons

Shared Knowledge Conference

The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a century. There are many benchmarks that have been used to validate neutronics codes, mostly for critical systems. Critical systems are systems where the neutron population from one generation to the next is the same. Subcriticality is when there are less neutrons in the next generation and supercriticality is when there are more neutrons in the next generation than there were in the previous. To calculate criticality, a set number of neutrons are started in a system. Those neutrons interact and the number ...


Numerical Modeling Of Fluid Flow In A Molten Salt Reactor, Alisa Machiwalla, Carnell Tate 2018 Kennesaw State University

Numerical Modeling Of Fluid Flow In A Molten Salt Reactor, Alisa Machiwalla, Carnell Tate

Georgia Undergraduate Research Conference (GURC)

Numerical Modeling of Fluid Flow in a Molten Salt Reactor

Molten Salt Reactors (MSRs) are a generation IV reactors that have been selected by the World Nuclear Association for its potential in the advancement of reactor sustainability, economics, safety, reliability, and proliferation-resistance. MSRs were originally designed in the 60s by Oak Ridge National Laboratory and have recently gained popularity. Literature shows differing mixed composition of uranium and fluoride salts being utilized in the reactor core. Depending on the mixed composition, each mix has different effects on the core overall temperature distribution. Temperature distribution within the reactor is important due to ...


An Overview Of Pebble-Bed Reactors, Paul Schwan, Julian Spangler, Isaac Naupa 2018 Kennesaw State University

An Overview Of Pebble-Bed Reactors, Paul Schwan, Julian Spangler, Isaac Naupa

Georgia Undergraduate Research Conference (GURC)

Pebble bed reactors (PBR) are a type of Generation IV nuclear reactor that offers remarkable advantages over traditional reactors in size, safety, and cost of construction. This makes PBRs a very attractive alternative to the more complex reactor designs currently operating while also offering a possible solution to increasing energy demands. There are currently a number of national and international companies in the nuclear industry working on the development and testing of PBRs. Even though several of the PBR designs are new, some designs resemble the original designs with modern technologies and materials. In this research study, a historical approach ...


Mcnp Modeling Of A Molten Salt Reactor, David Wall 2018 Kennesaw State University

Mcnp Modeling Of A Molten Salt Reactor, David Wall

Georgia Undergraduate Research Conference (GURC)

GURC Conference – Deadline: 9/21/2018

MCNP Modeling of a Molten Salt Reactor

David Wall and Chris Berry

Mentors:

Dr. Andrew Hummel

Dr. Tien Mun Yee

Dr. Jungkyu Park

Dr. Eduardo B. Farfán

Draft: 9/21/2018

A variety of national and international companies are looking into innovative and nontraditional nuclear reactor systems, known as Generation IV reactors. Recently, there has been an increased interest in a reactor type that uses molten salts of various compositions as nuclear fuel because of its economic and technological advantages. This research study is an exploratory exercise of the nuclear attributes of molten salt ...


An Overview Of Molten Salt Reactors – History, Design, And Future Prospects, Duncan Bohannon, Chase Casher 2018 Kennesaw State University

An Overview Of Molten Salt Reactors – History, Design, And Future Prospects, Duncan Bohannon, Chase Casher

Georgia Undergraduate Research Conference (GURC)

In the nuclear industry, there are several startup companies simulating, developing and testing new nuclear reactor designs. One of the many reactors being designed is the Molten Salt Reactor (MSR). MSRs were conceptualized and popularized by Oak Ridge National Laboratory in the 1960s. With the recent resurgence in interest regarding this type of reactor because of the economic and technical advantages, this research project aims to provide a historical context for their development, specific design specifications, and reactor core design modifications over time. In addition, this study focuses on various types of nuclear fuel, reactor geometries, potential moderator materials, and ...


10 - Dimensioning And Modeling Of A Molten Salt Reactor, Theron Crockett 2018 Kennesaw State University

10 - Dimensioning And Modeling Of A Molten Salt Reactor, Theron Crockett

Georgia Undergraduate Research Conference (GURC)

This will be a poster reviewing the scope of this project including all visuals and information found or created.


27 - Monte Carlo Simulation Of A Geiger Counter, Gamma-Ray Sources And Shielding, Luke Appling, Mayur Menon, David Wall 2018 Kennesaw State University

27 - Monte Carlo Simulation Of A Geiger Counter, Gamma-Ray Sources And Shielding, Luke Appling, Mayur Menon, David Wall

Georgia Undergraduate Research Conference (GURC)

Geiger counters are extensively utilized for measuring ionization radiation from alpha-particle, beta-particle, and gamma-ray sources. Geiger counters are used for radiation monitoring and field characterization in areas such as radiological protection, experimental physics, and nuclear industry. In this study, Monte Carlo simulations of a Geiger counter were completed using a Monte Carlo N-Particle Transport Code (MCNP). The purpose of this study was to expand the Geiger counter model to include gamma-ray shielding. To verify the code effectiveness, different simulations have been conducted using a variety of radiation sources (e.g., Cs-137 and Co-60) and materials including iron, lead, and concrete ...


Thermal Transport Study On Actinide Oxides Using Phonon Density Of States Calculation, Alex Resnick, Katherine Mitchell 2018 Kennesaw State University

Thermal Transport Study On Actinide Oxides Using Phonon Density Of States Calculation, Alex Resnick, Katherine Mitchell

Georgia Undergraduate Research Conference (GURC)

The thermophysical properties of nuclear fuels being developed in generation IV nuclear reactors are still being widely examined since the reactor’s operating performance is strongly correlated to the thermal transport properties of the fuel source. In this research, phonon density of states (DOS) are estimated for uranium dioxide (UO2), thorium dioxide (ThO2), and plutonium dioxide (PuO2) as these are all significant representations of the actinide oxide family. The crystalline structures of these fuels are altered to contain point defects in the form of primary atom vacancies, oxygen vacancies, and uranium substitution. Primary atom and oxygen vacancies ...


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