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Thermal Properties Of A Lif-Thf4 Molten Salt Fuel, Jackson Hill 2019 Kennesaw State University

Thermal Properties Of A Lif-Thf4 Molten Salt Fuel, Jackson Hill

Georgia Undergraduate Research Conference (GURC)

Molten salt reactors have seen an insurgence of interest and studies because of their high efficiency and their relatively compact design when compared to traditional reactors such as boiling water reactors. This study delves into the thermal properties of a LiF-ThF4 fuel for use in an MSR (Molten Salt Reactor).


Thermal Transport In Molten Salt Reactor Fuels, Bryce Atchley 2019 Kennesaw State University

Thermal Transport In Molten Salt Reactor Fuels, Bryce Atchley

Georgia Undergraduate Research Conference (GURC)

Thermal Transport in Molten Salt Reactor Fuels

Bryce Atchley, Jackson Hill, Jungkyu Park, Eduardo Farfan

In this research study, we explore the thermal transport property of Molten Salt Reactor (MSR) fuels by using molecular dynamics simulations. MSR has been drawing attention from researchers recently since it can run at high temperatures, yielding high energy production efficiency at relatively low amount of fuel mass. Its low operating pressure reduces the risk of a large break and loss of coolant significantly. Among different possible MSR fuels, LiF-ThF4 is selected to examine the thermal transport property of MSR fuels. Reverse Non-equilibrium molecular dynamics ...


Python Script For Homogeneous Aqueous Chemical Reaction Analysis And Associated Data Related To Radiolysis Simulations, Peter James Doyle, David Bartels 2019 University of Notre Dame

Python Script For Homogeneous Aqueous Chemical Reaction Analysis And Associated Data Related To Radiolysis Simulations, Peter James Doyle, David Bartels

Faculty Publications and Other Works -- Nuclear Engineering

No abstract provided.


The Impact Of The State-Level Concept On “Newcomers”: A Case Study Of The Kingdom Of Saudi Arabia, Thaqal Alhuzaymi, Ayodeji Babatunde Alajo 2019 Missouri University of Science and Technology

The Impact Of The State-Level Concept On “Newcomers”: A Case Study Of The Kingdom Of Saudi Arabia, Thaqal Alhuzaymi, Ayodeji Babatunde Alajo

Ayodeji B. Alajo

The International Atomic Energy Agency’s (IAEA) latest reports indicate a growing number of states (newcomers) considering the deployment of nuclear energy programs. In developing nuclear infrastructure, newcomers have to employ the prevailing standards to deploy the nuclear program in a secure, safe, and sustainable manner. State-Level Concept (SLC) refers to a comprehensive approach that uses information about a state’s nuclear facilities and capabilities to implement safeguards within the scope of the state’s safeguards agreement. SLC focuses on strengthening the effectiveness and improving the efficiency of the safeguards system considering the State as whole. SLC has been implemented ...


Low-Power Core Reconfiguration For Missouri S&T Reactor (Mstr), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo 2019 Missouri University of Science and Technology

Low-Power Core Reconfiguration For Missouri S&T Reactor (Mstr), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo

Ayodeji B. Alajo

The Missouri University of Sciences and Technology Reactor (MSTR) is pool-type research reactor which operates up to 200 kilowatt (kW). MSTR used for training and educating nuclear engineering students at Missouri S&T. A several of nuclear researches and irradiation experiments have been conducted in MSTR for example, neutron activation analysis (NAA), neutron radiography, radiolysis, image processing, etc. MSTR initial criticality took place on December 9, 1961. The first power level that MSTR operates at, was 10 kW. The power level alongside the core configuration was upgraded to the current ones, see Fig. 1. MSTR used light-water for moderation and ...


Analysis Of The Developing States In The Mena Region Seeking Civilian Nuclear Energy, With A Primary Focus On The Kingdom Of Saudi Arabia (Ksa) And The United Arab Emirates (Uae), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo 2019 Missouri University of Science and Technology

Analysis Of The Developing States In The Mena Region Seeking Civilian Nuclear Energy, With A Primary Focus On The Kingdom Of Saudi Arabia (Ksa) And The United Arab Emirates (Uae), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo

Ayodeji B. Alajo

The comprehensive analysis presented here attempts to ana­lyze “newcomer” states in the Middle East and North Africa (MENA), primarily the Kingdom of Saudi Arabia (KSA) and Unit­ed Arab Emirates (UAE), seeking to implement civilian nuclear energy according to their political and economic situations. By investigating their motivations and funding resources for fu­ture nuclear projects, this analysis provides guidance for these states in terms of their nuclear infrastructure and nonprolifera­tion. The overall approach of this analysis relies on the factors for the success of civilian nuclear energy programs identified in experiential studies conducted since the Atoms for ...


Enabling Mobile Neutron Detection Systems With Clyc, Matthew C. Recker 2019 Air Force Institute of Technology

Enabling Mobile Neutron Detection Systems With Clyc, Matthew C. Recker

Theses and Dissertations

Cs2LiYCl6:Ce3+ (CLYC) has the desirable property of being sensitive to both gamma rays and neutrons while producing waveforms suitable for pulse shape discrimination (PSD) to determine which radiation was detected. This dissertation examines the behavior of CLYC to support its further development for mobile and portable applications. First, the feasibility of performing PSD with CLYC and an inexpensive data acquisition system was examined. This system was able to clearly distinguish both events with a figure of merit of 1.42. Next, the performance of a SiPM was compared to a traditional PMT. Analysis showed that ...


Investigations Of Point Defects In Kh2Po4 Crystals Using Ab Initio Quantum Methods, Tabitha E. R. Dodson 2019 Air Force Institute of Technology

Investigations Of Point Defects In Kh2Po4 Crystals Using Ab Initio Quantum Methods, Tabitha E. R. Dodson

Theses and Dissertations

Potassium dihydrogen phosphate (KH2PO4, or commonly called KDP) crystals can be grown to large sizes and are used for many important devices (fast optical switches, frequency conversion, polarization rotation) for high powered lasers. The nonlinear optical material has a wide intrinsic transparency range. Intrinsic point defects are responsible for several short-lived absorption bands in the visible and ultraviolet regions that affect high-power pulsed laser propagation. The primary intrinsic defects have been experimentally detected in KDP using electron paramagnetic resonance (EPR) experiments. The defect models established thus far include (i) self-trapped holes, (ii) oxygen vacancies, and (iii) hydrogen ...


Point Defects In Lithium Gallate And Gallium Oxide, Christopher A. Lenyk 2019 Air Force Institute of Technology

Point Defects In Lithium Gallate And Gallium Oxide, Christopher A. Lenyk

Theses and Dissertations

Electron paramagnetic resonance (EPR), Fourier-Transform Infrared spectroscopy (FTIR), photoluminescence (PL), thermoluminescence (TL), and wavelength-dependent TL are used to identify and characterize point defects in lithium gallate and β-gallium oxide doped with Mg and Fe acceptor impurities single crystals. EPR investigations of LiGaO2 identify fundamental intrinsic cation defects lithium (VLi) and gallium (V2−Ga) vacancies. The defects’ principle g values are found through angular dependence studies and atomic-scale models for these new defects are proposed. Thermoluminescence measurements estimate the activation energy of lithium vacancies at Ea = 1.05 eV and gallium vacancies at Ea > 2 eV below the ...


Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham 2019 Missouri University of Science and Technology

Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham

Shoaib Usman

Monte Carlo radiation transport simulations were used to calculate the positron stopping profiles in tungsten positron moderator foils. Stopping profiles were numerically integrated with efficiency kernels derived from Green's function solutions of the 3D diffusion equation to determine the moderation efficiency in both the backscattering and transmission geometries. Stopping profiles and efficiencies were calculated for positron energies from 10 keV to 10 MeV and incident angles from 0° to 75°. The resulting efficiencies agreed with other calculated and measured values in the literature, especially when similar values of the positron diffusion length and surface emission branching ratio were used ...


Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham 2019 Missouri University of Science and Technology

Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham

Joseph T. Graham

Monte Carlo radiation transport simulations were used to calculate the positron stopping profiles in tungsten positron moderator foils. Stopping profiles were numerically integrated with efficiency kernels derived from Green's function solutions of the 3D diffusion equation to determine the moderation efficiency in both the backscattering and transmission geometries. Stopping profiles and efficiencies were calculated for positron energies from 10 keV to 10 MeV and incident angles from 0° to 75°. The resulting efficiencies agreed with other calculated and measured values in the literature, especially when similar values of the positron diffusion length and surface emission branching ratio were used ...


Experimental Investigation Of Steady-State And Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee 2019 University of New Mexico

Experimental Investigation Of Steady-State And Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee

Nuclear Engineering ETDs

The Critical Heat Flux (CHF) causes a rapid reduction of heat transfer coefficient with a rapid increase of cladding temperature, which may induce physical failure of the heated material. Understanding CHF phenomena and reliable prediction of the boiling behavior are needed to design a heat transfer system including nuclear reactors. Due to the complex nature of CHF, it is still an active research topic of interest. With an increasing interest in Accident Tolerant Fuel (ATF), CHF of ATF is essential topic of study for the detailed design of the fuel – cladding element and for the reactor safety analysis.

In this ...


Achieving High-Power Configuration In Missouri S&T Reactor (Mstr) For Potential Uprate, Thaqal Alhuzaymi, Ayodeji Babatunde Alajo 2019 Missouri University of Science and Technology

Achieving High-Power Configuration In Missouri S&T Reactor (Mstr) For Potential Uprate, Thaqal Alhuzaymi, Ayodeji Babatunde Alajo

Mining and Nuclear Engineering Faculty Research & Creative Works

Research reactor is a powerful tool because of its wide contribution, almost to each field of science. It’s considered to be an essential element for advancing research, development and improvement in nuclear industry. The main goal of research reactor is to produce neutrons which are beneficially used for a wide range of applications such as industrial, agricultural, medical, etc. Neutron spectrum impact it uses. Commonly, neutrons with low energy level, up to 0.5 eV, called thermal neutrons where neutrons with intermediate energy level, ranging from 0.5 eV to 0.10 MeV, called epithermal "resonance" neutrons and neutron ...


Low-Power Core Reconfiguration For Missouri S&T Reactor (Mstr), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo 2019 Missouri University of Science and Technology

Low-Power Core Reconfiguration For Missouri S&T Reactor (Mstr), Thaqal Alhuzaymi, Ayodeji Babatunde Alajo

Mining and Nuclear Engineering Faculty Research & Creative Works

The Missouri University of Sciences and Technology Reactor (MSTR) is pool-type research reactor which operates up to 200 kilowatt (kW). MSTR used for training and educating nuclear engineering students at Missouri S&T. A several of nuclear researches and irradiation experiments have been conducted in MSTR for example, neutron activation analysis (NAA), neutron radiography, radiolysis, image processing, etc. MSTR initial criticality took place on December 9, 1961. The first power level that MSTR operates at, was 10 kW. The power level alongside the core configuration was upgraded to the current ones, see Fig. 1. MSTR used light-water for moderation and ...


Neutronic And Cfd-Thermal Hydraulic Analyses Of Very-Small, Long-Life, Modular (Vsllim) Reactor, Luis M. Palomino 2019 Nuclear Engineering

Neutronic And Cfd-Thermal Hydraulic Analyses Of Very-Small, Long-Life, Modular (Vsllim) Reactor, Luis M. Palomino

Nuclear Engineering ETDs

Neutronic and CFD-thermal hydraulic analyses are performed of the Very-Small, Long-LIfe, and Modular (VSLLIM) nuclear reactor. This reactor was developed at the University of New Mexico’s Institute for Space and Nuclear Power Studies (UNM-ISNPS) to generate 1.0 – 10 MWth for extended periods without refueling. It offers passive operation and safety features and redundant control and would be fabricated, assembled and sealed in the factory. During nominal operation and after shutdown, the VSLLIM is cooled by natural circulation of in-vessel liquid sodium, with the aid of an in-vessel chimney and annular ...


Isotopically-Resolved Neutron Cross Sections As Probe Of The Nuclear Optical Potential, Cole Davis Pruitt 2019 Washington University in St. Louis

Isotopically-Resolved Neutron Cross Sections As Probe Of The Nuclear Optical Potential, Cole Davis Pruitt

Arts & Sciences Electronic Theses and Dissertations

Neutron scattering experiments provide direct access to the forces experienced by nucleons in the nuclear environment. Due to the experimental difficulty of cross section measurements with neutrons, isotopically-resolved neutron scattering cross sections are sorely needed as inputs for many nuclear models. This dissertation presents the results from a campaign of isotope-specific neutron total cross section measurements on 16,18O, 58,64Ni, 112,124Sn, and 103Rh from 3-450 MeV and elastic scattering differential cross section measurements on 112,nat,124Sn at 11 and 17 MeV. Equipped with these new data and with computational improvements to the Dispersive Optical Model (DOM), we ...


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.


Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham 2019 Missouri University of Science and Technology

Calculation And Tabulation Of Efficiencies For Tungsten Foil Positron Moderators, R. Alsulami, M. Albarqi, S. Jaradat, Shoaib Usman, Joseph T. Graham

Mining and Nuclear Engineering Faculty Research & Creative Works

Monte Carlo radiation transport simulations were used to calculate the positron stopping profiles in tungsten positron moderator foils. Stopping profiles were numerically integrated with efficiency kernels derived from Green's function solutions of the 3D diffusion equation to determine the moderation efficiency in both the backscattering and transmission geometries. Stopping profiles and efficiencies were calculated for positron energies from 10 keV to 10 MeV and incident angles from 0° to 75°. The resulting efficiencies agreed with other calculated and measured values in the literature, especially when similar values of the positron diffusion length and surface emission branching ratio were used ...


Interrogation Of Spent Nuclear Fuel Casks Using Cosmic-Ray Muon Computed Tomography, Daniel C. Poulson 2019 University of New Mexico

Interrogation Of Spent Nuclear Fuel Casks Using Cosmic-Ray Muon Computed Tomography, Daniel C. Poulson

Nuclear Engineering ETDs

Properly accounting and safeguarding spent nuclear fuel are key components in the International Atomic Energy Agency’s mission of non-proliferation. Currently, no instruments are deployed that are able to verify the spent nuclear fuel contents of dry storage casks. Cosmic-ray muons provide an ideal probe for the heavily shielded casks due to their ability to penetrate thick, dense materials. Coulombic scattering of the muons, to first order, is proportional to the Z2/A of the material; this makes it especially sensitive to actinides, such as uranium and plutonium. The combination of these traits allows muons to be used to image ...


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 ...


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