Nuclear Engineering Commons^™

A Review And Analysis Of Nuclear Hydrogen Production In Generation Iv Reactors, Arijit Saha Ayon, Ashiqur Rahman Alif, A. S. M. Nasim

International Journal of Nuclear Security

Hydrogen is becoming increasingly vital as a chemical element in the progress of human civilization. Hydrogen finds application in the creation of ammonia, the manufacturing of nitrogen-based fertilizers, and a wide range of organic compounds, including methanol and propulsion fuel for space exploration missions. Additionally, there are ongoing experiments in the automotive industry to harness hydrogen-based fuel cells as an alternative power source. In modern technology, multiple methods and strategies for hydrogen production originate from diverse sources, such as fossil fuels, renewable energy, nuclear energy, and more. Generation IV nuclear reactors significantly affect the production of hydrogen. These reactors operate …

Remote Detection Of Leaks In High Level Waste Storage Tanks, Hunter Frey

UNLV Theses, Dissertations, Professional Papers, and Capstones

The purpose of this research was to characterize three devices potentially capable of remotely detecting signatures of a leak from high-level waste (HLW) storage tanks, specifically ones found at the Savannah River Site and the Hanford Site. The hazard HLW found within these tanks include ¹³⁷Cs, a gamma-ray emitter, and ⁹⁰Sr, an electron emitter leading to heat generation. These pose health risks to the personnel and maintenance problems and environmental safety issues if released to the environment. Additionally, pinpointing the location of a leak is a task that could lead to the mitigation of excess waste leaking from …

Investigative Research On Design Parameters And Criticality Models For Microreactors, Cameron Jensen

UNLV Theses, Dissertations, Professional Papers, and Capstones

With increased energy demand and the desire to reduce reliance on fossil fuels, nuclear power will need to play a prominent role in achieving carbon-free energy independence. Large nuclear reactors are necessary to meet this objective. However, they are expensive and take a long time to build. For remote locations (e.g., military bases) and smaller communities, large nuclear reactors would not be feasible or cost effective. Small reactors (microreactors) can fill this necessary gap. These reactors would be factory-built, delivered quickly, and operated with high intrinsic levels of safety. With microreactors still in conceptual and testing states, there is a …

Tnt Equivalence: Measuring, Validating, And Appending Binary Energetics To The Literature, Gracie Mae James, Rachel Bauer, Alexander Douglas, Catherine E. Johnson

Undergraduate Research Conference at Missouri S&T

TNT equivalency is a standard used to measure and quantify the effects of energetic materials. Using these equivalencies, the safety factors for minimum distances and storage of explosives are determined. Having a known TNT equivalence of energetic materials also helps estimate potential blast damage and risks for individuals. The TNT equivalencies for numerous energetic materials, such as binaries, have no published values, but are regularly used in industry, military, and research testing. To determine TNT equivalence, three tests were performed: 1) a plate dent test for direct dent comparison, 2) air blast tests to measure air overpressure and calculate impulse, …

Tnt Equivalence Of Binary Energetics, Gracie Mae James

Undergraduate Research Conference at Missouri S&T

TNT equivalency is a standard used to measure and quantify the effects of energetic materials. Using these equivalencies, the safety factors for minimum distances and storage of explosives are determined. Having a known TNT equivalence of energetic materials also helps estimate potential blast damage and risks for individuals. The TNT equivalencies for numerous energetic materials, such as binaries, have no published values, but are regularly used in industry, military, and research testing. To determine TNT equivalence, three tests will be performed: 1) a plate dent test, 2) air blast tests to measure air overpressure and calculate impulse, and 3) velocity …

Improving Criticality Safety Benchmark Coverage By Developing A Benchmark Evaluation Of The Unm Agn-201m Reactor, Rowdy Davis

Nuclear Engineering ETDs

This research aimed to improve the benchmark coverage of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook and the International Reactor Physics Experiment Evaluation Project (IRPhEP) with respect to High-Assay, Low-Enriched Uranium Fuel (HALEU). This was accomplished by creating a benchmark of the University of New Mexico’s Aerojet General Nucleonics model 201-M reactor and submitting it to the ICSBEP. This research then aimed to quantify to what extent this benchmark improves coverage of the benchmark suites for HALEU and TRISO fuel applications. This investigation utilized WHISPER, TSUNAMI-IP, and TSURFER with 36 application cases developed in SCALE and 2,929 experiments …

Pulsed-Power Neutron Production With Deuterated Polymer Accelerator Targets, Anthony O. Hagey, Juan J. Manfredi, Whitman T. Dailey, S. L. Jackson, E. R. Kaiser, J, W. Schumer

Faculty Publications

This document presents an investigation of the effect of deuterated accelerator targets on the neutron fluence from a local mass injection dense plasma focus (LMIDPF) driven by the United States Naval Research Laboratory's (NRL) Hawk pulsed-power generator. Deuterated targets were made using two methods: a well-established thin-film casting technique for flat targets and a more novel additive manufacturing technique that allowed targets to be three-dimensional (3D) printed in both flat and conical geometries. These targets were then tested during neutron-producing experiments conducted using Hawk, and theneutron fluences measured for the various target types were compared. Additive manufacturing was used as …

Small Modular Reactor And Advanced Reactor Feasibility Study Interim Report, Purdue University Administrative Operations, Purdue University School Of Nuclear Engineering, Duke Energy

Administrative Operations Reports

No abstract provided.

Design And Analysis Of Free Piston Stirling Engines For Microreactor Applications, Phat D. Doan

Nuclear Engineering ETDs

Through the development of microreactors, a free piston Stirling engine (FPSE) is an excellent candidate to support the development of the microreactors applications. This study proposes a 20 kWe design of the FPSE for microreactor applications. The model has been developed and analyzed through a MATLAB code that was verified and benchmarked with both RE-1000 engine’s experiment data and Sage software. The MATLAB code has been developed from scratch using the first and second order approximation to simulate the engine’s steady state operation. There are three operating conditions that were applied to the code such as ideal isothermal, ideal adiabatic, …

Insen 2023 Yearly Updates, Walid Metwally, Matteo Gerlini, Cristen Ford, João Claudio Batista Fiel J.C.B.F., Dr. Alpana Goel

International Journal of Nuclear Security

The International Nuclear Security Education Network (INSEN) is the primary international network for nuclear security educational initiatives. INSEN plays a central role in fostering collaboration and knowledge-sharing among nuclear security education experts worldwide. In the wake of the global pandemic, INSEN remained committed to strengthening nuclear security education and resumed in-person activities. The International Atomic Energy Agency (IAEA) confirmed its continued dedication and support to the network’s mission and presented new activities aimed at elevating global nuclear security efforts.

Throughout the year and during the annual and leadership meetings, working groups showcased their vibrant work and presented innovative ideas, invigorating …

Synergistic Effects Of Neutron And Gamma Radiations On The Electrical Properties Of Mosfets, Jackson T. Piechowski

Theses and Dissertations

In many radiation environments, electronic assets are exposed to a wide variety of species of radiation. This thesis studies the effect of sequential exposure of MOSFETs to neutron and gamma radiation. 27 Goford Semiconductor GT060N04T MOSFETs with gate thickness ∼500 nm were exposed to gamma radiation from a Cesium-137 source and mixed gamma and neutron radiation from a Californium-252 source with total amounts of ionizing radiation dose, neutron fluence, and order of irradiation varied to determine if synergistic effects of neutron and gamma irradiation can be measured. Neutron fluence values as low as 3.45x109 and as high as 3.40x1010 neutrons/cm2 …

Neutron Spectrum Unfolding From Activation Foils Irradiated In Gamble Ii Using Deuterated Polyethylene Anodes, Christopher J. Smith

Theses and Dissertations

Neutrons can cause irreparable harm to electronics, and experiments are needed to understand their effects fully. This work explores using pulsed power, which is low-cost compared to other sources, to create a useful neutron-rich environment. Deuterated polyethylene was used as anode and catcher material to generate the neutrons from the Deuterium-Deuterium (DD) fusion reaction. A simple, effective, and repeatable method was employed to directly cast deuterated polyethylene onto polyethylene sheets to fabricate the anode and catcher. The DD reactions were made by an ion beam-driven pulsed power generator, Gamble II, with the catcher located in the cathode. Zinc, copper, aluminum, …

Personal Dosimeter Testing For High Altitude Air Crew, Seth D. Bacon

Theses and Dissertations

In 2014 the Thermo Scientific N2 electronic personal dosimeter became the aircrews’ sole means to record ionizing radiation dose. The production of this dosimeter was discontinued in July of 2021, motivating the Air Force to seek a flight-certifiable replacement. The Thermo Scientific Trudose NG, Mirion DMC 3000, and Fuji NRF-51 electronic personal dosimeters, as well as the Landauer InLight optically stimulated luminescent dosimeter, were subjected to mixed gamma and fast neutron fields simulating a high-altitude flight environment. Dosimeters are evaluated on their consistency and accuracy in reporting dose and compared to the current N2 dosimeter’s reported dose.

Gamma Protection Factor For A Surrogate Armored Vehicle Exposed To The Us Army Fast Burst Reactor, Ian J. Poropat

Theses and Dissertations

This work measures the Gamma Protection Factor (GPF) of a steel cube, which is meant to serve as a surrogate for armored vehicles. The GPF is measured at the White Sands Missile Range Fast Burst Reactor (FBR) and is modeled using MCNP® v6.2 transport simulation software. When exposed to the FBR, the GPF is found to depend roughly linearly on the distance between the reactor core and steel cube. The GPF is determined to be 1.176 ± 0.00067 at 9.21 m, 1.098 ± 0.0011 at 26.16 m, and 1.033 ± 0.00082 at 42.92 m. MCNP® estimates the GPF for the …

Two-Group Drift-Flux Model For Dispersed Gas-Liquid Flow In Large-Diameter Pipes, Hossein Barati, Takashi Hibiki, Joshua P. Schlegel, Naofumi Tsukamoto

Nuclear Engineering and Radiation Science Faculty Research & Creative Works

Interfacial Heat and Mass Transfer Are Prevalent in Industrial Processes. the Interfacial Transfer Rate Can Be Obtained by the Product of their Fluxes and Interfacial Area Concentration (IAC) Calculated by the Interfacial Area Transport Equation (IATE). Bubbles Show Different Behavior According to their Sizes. Hence, Bubbles Are Classified into Two Groups. Consequently, Two-Group IATE is Required Causing to Use of Two Gas Momentum Equations Leading to More Complexity. the Present Study Suggests a New Reliable Two-Group Drift-Flux Modeling to Reduce the Two Gas Momentum Equations to One Gas Mixture Momentum Equation for Gas-Liquid Flow in Large-Diameter Pipes. the Model is …

Validation Of Athlet With Purdue University Multi-Dimensional Integral Test Assembly (Puma) Test, Emin Fatih Ozdem

Masters Theses

"Following the Three Mile Island Unit 2 (TMI-2) disaster, the development of a diagnostic system for emergency situations in a nuclear power plant was identified as an essential research area to strengthen the safety of nuclear power plants. A real-time estimation system of vital safety parameters on the main side of a PWR (Pressurized Water Reactor) facility was investigated since precise post-event scenario estimations are thought to be a crucial component of the diagnostic system. The alarm system of the plant can detect an SB-LOCA (Small Break Loss-Of-Coolant-Accident), but there were a couple of potential long-term transient occurrences. The accident …

Investigating Accident-Tolerant Cladding In A Molten Salt-Cooled Micro-Reactor Using Multi-Physics Analysis And Uncertainty Quantification, Alexander Niles Foutch

Masters Theses

"Renewed interest in nuclear safety has resulted in development of accident-tolerant materials, such as cladding. Although developed for light water reactors, their use in more advanced reactors would save time and development costs for other new materials. This paper performed a Multiphysics investigation into the power profile, thermodynamics, heat transfer, and tensor mechanics of four candidate materials (Haynes 230, Zircaloy-4, FeCrAl, and SiC-SiC), using the highly benchmarked Kilo power design as an example of a high-temperature, highly enriched, sodium-cooled microreactor environment.

From neutronic code MCNP, no significant difference in power profile was found among the four. Using finite element software …

Computational Fluid Dynamics Analysis Of Thermal-Hydraulic Phenomena In Nuclear Reactor Systems, Mehedi Hasan Tusar

Masters Theses

"A computational analysis of thermal-hydraulic processes in nuclear reactor systems is performed, leveraging Computational Fluid Dynamics (CFD) to advance the design and ensure the safety of nuclear reactors. Divided into two primary sections, the initial part examines thermal-hydraulic behavior in the Replacement Research Reactor (RRR) operating at 20 megawatts and evaluates potential enhancements for the Missouri University of Science and Technology Reactor (MSTR) to operate at an increased capacity of 2 megawatts from the existing 0.2 megawatts. Detailed simulations reveal insights into flow characteristics, temperature distributions, and pressure drops, highlighting the effective use of realistic and porous media modeling techniques …

Fluid Flow And Thermal Performance Investigation Of Twisted Elliptical Tubes For Use In High Prandtl Number Systems, Connor F. Donlan

Theses and Dissertations

The development of clean energy systems is paramount to reducing mankind's climate impact. These clean energy systems include solar, wind, and nuclear power where nuclear power shows a reduced lifetime carbon dioxide footprint per kilowatt hour compared to other sources [102]. Advanced nuclear reactors, fusion energy systems, and concentrated solar power designers are looking at using molten salt heat transfer fluids and improved heat exchanger design to increase power production and efficiency of clean energy systems. The improving heat transfer within the main heat transfer components within advanced nuclear reactors will enable increased efficiencies and power production.

Heat transfer improvements …

A Case Study Assessing The Integration Of Nuclear Safety And Security In Facilities Using A Monte Carlo Simulation Aided Analytical Hierarchy Process, Theodore A. Thomas, Shraddha Rane, Jason Timothy Harris

International Journal of Nuclear Security

Nuclear safety and security are essential in all operations using nuclear and radioactive materials. Even though both elements are important, the evolution of these programs has not developed at the same rate. As such, their integration has been met with challenges. This study analyzed the potential for synergy across different criteria and settings when integrating nuclear safety and security. The criteria included eight points where overlap could be identified between nuclear safety and security. Three work settings—industrial, medical, and research—were evaluated. Responses were collected from nine individuals who worked with nuclear materials in various capacities and different nuclear work settings. …