Open Access. Powered by Scholars. Published by Universities.®

Nuclear Engineering Commons

Open Access. Powered by Scholars. Published by Universities.®

1,365 Full-Text Articles 1,719 Authors 250,985 Downloads 44 Institutions

All Articles in Nuclear Engineering

Faceted Search

1,365 full-text articles. Page 1 of 31.

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.


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 ...


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 ...


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 ...


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 ...


Heat Transfer Comparison Of Varied Pebble Sizes And Packing Arrangements In A Pebble-Bed Reactor, Julian Spangler 2018 Kennesaw State University

Heat Transfer Comparison Of Varied Pebble Sizes And Packing Arrangements In A Pebble-Bed Reactor, Julian Spangler

Georgia Undergraduate Research Conference (GURC)

Pebble bed reactors are more cost efficient when heat transfer is optimized. In a pebble-bed reactor, optimizing heat transfer involves the analysis of complex flow. Therefore, computational fluid dynamics was used to simulate fluid movement in a structured cubic packing arrangement with a purpose in finding an optimal size of pebbles that will yield the fastest rate of heat transfer. The simple cubic pebble arrangement was used to determine if pebble size was key to optimizing heat transfer in the reactor. More complex arrangements of pebbles were used as comparison to the simple cubic packing in order to determine if ...


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 ...


Direct Synthesis Of Radioactive Nanoparticles Involving Neutrons, Carlos Henry Castano Giraldo, Maria Camila Garcia Toro, Brian Michael Mills 2018 Missouri University of Science and Technology

Direct Synthesis Of Radioactive Nanoparticles Involving Neutrons, Carlos Henry Castano Giraldo, Maria Camila Garcia Toro, Brian Michael Mills

Mining and Nuclear Engineering Faculty Research & Creative Works

A method to synthesize radioactive nanoparticles includes the production of metallic and multimetallic nanoparticles in a single step by providing an aqueous solution of the metal precursor, and irradiating the aqueous solution thereby producing nanoparticles. The obtained nanoparticles include one or more radioactive isotopes of gold, such as 198Au and 199Au as well as radioisotopes of silver when the obtained nanoparticles are bimetallic. The aqueous solution is irradiated in a radiation field that includes neutrons and gamma rays. The radiation field may be provided by a nuclear reactor. The aqueous solution may include silver, and bimetallic nanoparticles may be produced ...


Spin Alignment Generated In Inelastic Nuclear Reactions, Daniel Hoff 2018 Washington University in St. Louis

Spin Alignment Generated In Inelastic Nuclear Reactions, Daniel Hoff

Arts & Sciences Electronic Theses and Dissertations

The spin alignment of inelastically excited 7Li projectiles, when the target remains in its ground state, was determined through angular-correlation measurements between the breakup fragments of 7Li_ (_ + t). It was found that 7Li_ is largely aligned along the beam axis (longitudinal) in this type of inelastic reaction, regardless of the target. This longitudinal alignment is well described by DWBA calculations, which can be explained by an angular-momentum-excitation-energy mismatch condition. These calculations also explain the longitudinal spin alignment of excited nuclei in several other systems, showing the phenomenon is more general. The experiment involving 7Li was performed at the Texas ...


Incorporating Collisions And Resistance Into The Transition From Field Emission To The Space Charge Regime, Samuel D. Dynako, Adam M. Darr, Allen L. Garner 2018 Purdue University

Incorporating Collisions And Resistance Into The Transition From Field Emission To The Space Charge Regime, Samuel D. Dynako, Adam M. Darr, Allen L. Garner

The Summer Undergraduate Research Fellowship (SURF) Symposium

Advancements in microelectromechanical systems (MEMS) and microplasmas, particularly with respect to applications in combustion and biotechnology, motivate studies into microscale gas breakdown to enable safe system design and implementation. Breakdown at microscale deviates from that predicted by Paschen’s law due to field emission—the stripping of electrons from the cathode in the presence of strong surface field—and follows the Fowler-Nordheim (FN) law. As injected current increases at this length scale, electrons accumulate in the gap and FN electron emission becomes space charge limited, leading to the Child-Langmuir (CL) law at vacuum and the Mott-Gurney (MG) law at high ...


A Security Approach For The Example Sodium Fast Reactor, Christian X. Young, Robert S. Bean 2018 Purdue University

A Security Approach For The Example Sodium Fast Reactor, Christian X. Young, Robert S. Bean

The Summer Undergraduate Research Fellowship (SURF) Symposium

Increases in the spread of nuclear technology and the rise of non-state terrorism in the modern era has proved the need for effective security approaches to new nuclear facilities. Many documents about security approaches for nuclear plants are non-public material, however, making it difficult to teach others about the basics of security design. To alleviate this issue, we used available texts in the security realm to design a security approach for the Generation IV International Forum’s Example Sodium Fast Reactor. Our approach utilized infrared, microwave, fiber optic, and other advanced technologies to provide security for the special nuclear material ...


Sonomechanical Enhanced Sparging Techniques For Advanced Reactor Applications, Floren V. Rubio 2018 University of New Mexico

Sonomechanical Enhanced Sparging Techniques For Advanced Reactor Applications, Floren V. Rubio

Nuclear Engineering ETDs

The fluoride salt cooled high temperature reactor (FHR) is a Generation IV advanced reactor design that has potential to produce efficient, low carbon, and safe energy. But, there are significant engineering challenges that need to be addressed before the deployment of this reactor. One of the key challenges is tritium release mitigation and sequestration. Because the FHR utilizes a eutectic LiF-BeF2 (flibe) salt as a coolant, the coolant is a significant source of tritium.

High-power ultrasonics have been used in many industrial process streams such as food processing, metal production, chemical production, and pharmaceutical manufacturing. Techniques and concepts from these ...


Recommended Corrective Security Measures To Address The Weaknesses Identified Within The Shapash Nuclear Research Institute, Khadija Moussaid, Oum Keltoum Hakam 2018 University of Ibn Tofail

Recommended Corrective Security Measures To Address The Weaknesses Identified Within The Shapash Nuclear Research Institute, Khadija Moussaid, Oum Keltoum Hakam

International Journal of Nuclear Security

The Shapash Nuclear Research Institute (SNRI) data book was issued by the International Atomic Energy Agency (IAEA) in 2013. The hypothetical facility data book describes the hypothetical site, which is divided into two areas: the low-security area, known as the administrative area, and the very high-security area, known as the protected area. The book contains detailed descriptions of each area’s safety and security measures, along with figures of multiple buildings in both areas, and also includes information about the site’s computer networks.

This paper aims to identify security weaknesses related to the institute’s location, the Administrative Area ...


Actinium-225 Production Via Different Irradiation Beams Of Thorium-232, Naser Burahmah 2018 University of Tennessee, Knoxville

Actinium-225 Production Via Different Irradiation Beams Of Thorium-232, Naser Burahmah

Nuclear Engineering Reports

No abstract provided.


Interdigital Capacitance Local Non-Destructive Examination Of Nuclear Power Plant Cable For Aging Management Programs, S. W. Glass, L. S. Fifield, Nicola Bowler, Aishwarya Sriraman, W. C. Palmer 2018 Pacific Northwest National Laboratory

Interdigital Capacitance Local Non-Destructive Examination Of Nuclear Power Plant Cable For Aging Management Programs, S. W. Glass, L. S. Fifield, Nicola Bowler, Aishwarya Sriraman, W. C. Palmer

Materials Science and Engineering Publications

This Pacific Northwest National Laboratory milestone report describes progress to date on the investigation of non-destructive test methods focusing on local cable insulation and jacket testing using an interdigital capacitance (IDC) approach. Earlier studies have assessed a number of non-destructive examination (NDE) methods for bulk, distributed, and local cable tests. A typical test strategy is to perform bulk assessments of the cable response using dielectric spectroscopy, Tan , or partial discharge followed by distributed tests like time domain reflectometry or frequency domain reflectometry to identify the most likely defect location followed by a local test that can include visual inspection, indenter ...


Digital Commons powered by bepress