Nuclear Engineering Commons^™

Molecular Dynamics Study For Tritium Adsorption On Novel Materials, Jason Viscardi, Benjamin Robinson, Asher Flanagan

Symposium of Student Scholars

In this study, novel materials will be researched, and their potential uses for tritium control. 12 studies have been collected on various materials that give a solid foundation for future research that will be conducted regarding tritium control. All these studies used molecular dynamics simulation (MDS) to generate results. The first paper found from a university in Crete, Greece discussed pillared graphene to store hydrogen in a novel 3D carbon nanostructure in which pore size and surface area can be adjusted to suit the need. This was the first of several studies that aim to arrange the graphene in such …

Study Level Recovery Processes Of Thorium And Several Rare Earth Elements From Monazite Ore, Makayla Hyde, Jaclyn Choate

EURēCA: Exhibition of Undergraduate Research and Creative Achievement

Monazite ore is composed of several minerals including several rare earth element (REE) and thorium phosphates. Many past research projects have looked at the extraction of REE from monazite ore but have discarded the thorium phosphate compound as waste. Since thorium could be a possible fuel for state-of-the-art future nuclear reactors, this research focuses on a way to recover thorium from the monazite ore. The overall purpose of this research is to develop a conceptual recovery process that recovers thorium dioxide from monazite ore. In some parts of the world where uranium sources are limited; then, thorium could be used …

Sterilizing Masks With Uvc Light, Christopher Focht

Symposium of Student Scholars

This experiment focused on the construction and testing of a UVC light box and the treatment of facemasks with UVC light. Exposure rates were calculated and measured to ensure efficacy of the light box. Masks were contaminated with bacteria and exposed for set time intervals, after which the bacteria were collected, cultured, and counted. Early results show that the masks in the box had no bacteria survive past ten seconds. This research is ongoing with different bacteria strains and mask types.

Diversifying Nuclear Technology: A Technical Analysis On Small Modular Reactors And Its Impact On Nuclear Energy Policy, Carolina Lugo Mejia, Marcos Lugo

Helm's School of Government Conference - American Revival: Citizenship & Virtue

The energy policy debate in the United States has revolved around the diversification of energy sources while promoting advantageous economic profits. One drive for this has been the discussion of anthropogenic, environmental endangerment concerns (Vlassopoulous 2011, 104). However, despite the environmental concerns, the U.S. has for some time only relied on one type of energy source—fossil fuels. Fossil fuels are categorized as natural gas, coal, petroleum, and other gases responsible (U.S. Energy Administration 2019). Natural gas is responsible for 38.4%, coal for 23.4%, petroleum for 0.4%, and other gases for 0.3% of the U.S.’s electrical generation (U.S. Energy Administration 2019). …

Leveraging Commercial Nuclear Reactors To Power Space Exploration, Ben Johnson

Utah Space Grant Consortium

This study is aimed at exploring the adaptation of commercial nuclear reactors as an alternative to NASA’s current high-power fission reactor systems, particularly with respect to applications on the surface of Mars. The study concludes that while the Kilopower architecture is brilliantly poised to provide affordable, near-term power in the 1-10 kilowatts electric (kWe) range, the financial barrier to higher power scaling of such systems is significant. This financial barrier adds risk to the development of greater than 10kWe systems and is likely to result in the failure to successfully scale the technology to higher powers for space exploration applications. …

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 …

Overview Of The United States Withdrawal From The Intermediate-Range Nuclear Forces Treaty, William Steinberger

Purdue Workshop on Nonproliferation: Technology and Approaches

The Intermediate-Range Nuclear Forces (INF) Treaty symbolized the end of the Cold War and the likely termination of thistreaty marks the beginning of a new era. On February 1, 2019, Secretary of State Pompeo announced that the United States(U.S.) would withdrawal from the INF Treaty citing repeated violations by the Russian Federation as cause for withdrawal. Asearly as 2008, U.S. intelligence agencies reported missile testing by the Russian Federation of a cruise missile system that couldhave a range between the limits outlined by the INF Treaty. The Russian Federation has repeatedly denied the allegations andhas suggested that the U.S. is …

Initial Active Interrogation Experiments At The University Of Michigan Linear Accelerator Laboratory, Christopher Meert, Cameron A. Miller, Shaun D. Clarke, Sara A. Pozzi

Purdue Workshop on Nonproliferation: Technology and Approaches

To support the mission of the Countering Weapons of Mass Destruction Office of the Department of Homeland Security, the Detection for Nuclear Nonproliferation group is researching active interrogation techniques and the development of new detection algorithms for fast neutron spectroscopy. The Countering Weapons of Mass Destruction Officehas loaned us a Varian M9 linear accelerator (linac), helium-3 detectors, boron-coated straw detectors, and perfluorocarbondetectors as part of this research, providing a variety of tools to conduct our experiments.In the summer of 2018, a thorough licensing process concluded, and preliminary experiments commenced. Later in the year, the facility was approved to possess and …

Purdue Conference On Active Nonproliferation, Trent Baker, Ray Benitez, Jack Mcmahan, Josh Monge, Kayla Robinson

Purdue Workshop on Nonproliferation: Technology and Approaches

Design a small modular reactor that is easily transportable for use in disaster relief as well as remote military outposts. A rail shippable reactor gives quick and easy transportation from one part of a country to another. The reactor must have a three MWe production capacity to ensure the reactor has the performance to power larger government facilities, such as hospitals and water treatment plants. The reactor must have enough fuel for a six-month minimum fuel cycle. Atmospheric cooling only provides the ability to reject heat to the atmosphere, minimizing the weight requirements. Uranium fuel will have a maximum of …

Regulatory Design For Transport Security Regulations Of Nuclear And Other Radioactive Material, Marc R. Fialkoff

Purdue Workshop on Nonproliferation: Technology and Approaches

A cornerstone within a nuclear security regime of a country is a legislative and regulatory framework that both regulates the individuals using radioactive and nuclear materials, but also regulates the regulators for their commitments under International Law. When drafting nuclear law and regulations, both technical and legal expertise is needed to ensure the regulation meets the technical requirements for security, but also is legally enforceable within a country’s jurisdiction. While the Primary Nuclear Law, or Enabling Act provides establishes the Competent Authority and responsibilities for nuclear security, regulatory development is where the proverbial, rubber meets the road for requirements. The …

The Effects Of The Urban Environment On Background Neutron Flux, Eric Reddick, John Burkhardt, Marshall Millett

Purdue Workshop on Nonproliferation: Technology and Approaches

This project will measure the neutron background inan urban environment using United States Naval Academy’s(USNAs)high sensitivity neutron detection system, called the Large Neutron Sensor (LNS).The background neutron flux represents noise and affects our ability to identify a signal from illicit source material, including plutonium.As the neutron background essentially rains down from high energy cosmic ray events in our upper atmosphere, the shielding effect of skyscrapers in an urban environment on the ground level background is of interest.Witha characterization of the neutron background in this environment, end users will be able to optimize the effectiveness of survey protocols and alarm algorithms.

Purdue Conference On Active Nonproliferation, Angela Di Fulvio, Yoann Altma, Marc G. Paff, Al Hero, Sara A. Pozzi

Purdue Workshop on Nonproliferation: Technology and Approaches

One major problem with nuclear security measurements involves source identification inthe presence of low signal-to-background ratio. This scenario iscommon to several applications, ranging from radiation identification atportal monitors to radiation source search with unmanned vehicles. In this context of identification of a large variety of sources, including natural and medical sources, sensitive sources of particular interest, but also potentially new/unknown sources for which no reference measurement is available, statistical methods are particularly appealing for their ability to capture the random nature of the measurements. Among them, Bayesian methods form a generic framework allowing for uncertainty quantification and propagation, which is …

Radiation Detection, Measurement, And Visualization Assisted By Virtual And Augmented Reality, Erik Medhurst, Rizwan Uddin

Purdue Workshop on Nonproliferation: Technology and Approaches

Localizing a radiation source in an urban environment is a challenge in nuclear nonproliferation and radiation detection. Mobile radiation sensor networks can be sent into an area of interest to collect count rate measurements at many locations in an attempt to find the radiation source. However, there are numerous factors that cause fluctuations in background count rate such as time and location, and these factors make it challengingto analyze thecollected data. Displaying these measurements in a virtual model has contextualized them and made it easier to determine if environmental factors are introducing false positives. A virtual model has been shown …

Exploring Laser Induced Breakdown Spectroscopy (Libs) For Post-Detonation Nuclear Forensics Debris Analysis, Justin Knoll, Chad Schools, David Fobar

Purdue Workshop on Nonproliferation: Technology and Approaches

In the unlikely but catastrophic event of a nuclear terrorist attack our government leadership will need reliable information to rapidly inform critical decisions. This research explores the use of Laser Induced Breakdown Spectroscopy (LIBS) as a potential analysis tool in the National Technical Nuclear Forensics process. The current state of post detonation nuclear forensics requires ground and air samples be collected and shipped to state-of-the-art laboratories for radiochemical analysis. The samples undergo many measurements and useable data is produced as these measurements are completed. This data flows back into the process to guide additional measurements and inform the process of …

Purdue Conference On Active Nonproliferation, Daniel Hartman, Sean Alcorn, Tyler Naughton, Chris Duff, Gavin Webb

Purdue Workshop on Nonproliferation: Technology and Approaches

Conference for the discussion of nuclear nonproliferation

Analysis Of Proliferation Resistance Of Small Modular Reactors (Smr) For The Expansion Of Civilian Nuclear Power Systems, Abdus Sattar Mollah, Abdus Sattar Mollah Prof.

Purdue Workshop on Nonproliferation: Technology and Approaches

Analysis of Proliferation Resistance of Small Modular Reactors (SMR) for the Expansion of Civilian Nuclear Power Systems A. S. Mollah Department of Nuclear Science and Engineering Military Institute of Science and Technology Mirpur Cantonment, Dhaka-1216, Bangladesh Abstract Nuclear energy has the potential benefit to make an important contribution for mitigating greenhouse gas (GHG) emissions that cause climate change. Expanding nuclear energy capacity worldwide based on large centralized facilities poses many challenges and risks due to the large capital costs, important safety issues, obstructive public attitude, and persistent concerns about proliferation-that is, the intentional misuse of nuclear technology and material. SMRs, …

A Characterization Of Undersea Neutron And Capture Gamma Signatures Resulting From Special Nuclear Material On A Maritime Vessel, Elizabeth Troy

Purdue Workshop on Nonproliferation: Technology and Approaches

Special Nuclear Materials (SNM) located aboard ships emit radiation that may be detectable in the undersea environment. An Unmanned Underwater Vehicle (UUV) could be equipped with detection capabilities to determine whether commercial or private vessels are carrying SNM prior to reaching port. Additional research is needed improve such a UUV’s ability to detect and discriminate between types of SNM and reduce false- positive detections. This research builds on past work by C. T. McKay to provide a higher fidelity characterization of detectable radiation signatures from SNM in the undersea environment with a focus on plutonium-bearing SNM. 252Cf will be used …

Multi-Grid Acceleration Scheme For Neutron Transport Calculations Using Optimally Diffusive Cmfd Method, Lakshay Jain, Ramamoorthy Karthikeyan, Umasankari Kannan

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Method of characteristics (MOC) is one of the most efficient deterministic techniques for high fidelity neutronic analysis of complex and heterogeneous reactor problems. However, the conventional MOC inner-outer iteration scheme suffers from poor convergence speeds for problems with large scattering to transport cross-section ratio and/or large dominance ratio. This creates a serious hindrance for its effective application to realistic reactor problems. A High Order – Low Order (HO-LO) multi-grid scheme using optimally diffusive coarse mesh finite difference (odCMFD) method has been introduced for improving the performance of code DIAMOND, an assembly level neutronic analysis code based on MOC and unstructured …

Review Of Fuel Management Practices At Various Stages Of Nuclear Fuel Cycle In Phwrs In View Of Environmental Effects, Ravi Kumar Bansal, H. S. Sharma Dr, R. K. Singh Dr, P. N. Prasad

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Nuclear Power is emerging as a promising source of environmentally benign energy source alternate from both pollution free environment as well as solution to global warming because of minimal carbon footprint. However, release of radiation and radioactive contamination during fuel cycle operations comprising the optimum fuel utilization in Nuclear Reactors, still remains a challenge to contain the sources of radiation and contamination away from public domain. This review article envisages qualitatively the environmental effects w.r.t. radiation during flow of Natural Uranium fuel used in Indian Pressurized Heavy Water Reactors (IPHWRs) at various stages of mining, fabrication, transportation, operation in nuclear …

Xenon Dynamics Of Ahwr, Arindam Chakraborty, Baltej Singh

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Large core reactors where the core dimension is significantly large compared to the migration length of neutron are more susceptible to xenon instability due to local perturbations. Advanced Heavy Water Reactor (AHWR) is being designed for on-power refueling. Therefore, refueling or movement of control devices in AHWR causes local perturbation. Preliminary modal analysis of AHWR equilibrium core also showed that the eigenvalue separation between fundamental mode and 1st azimuthal mode is small indicating its susceptibility to xenon oscillation in azimuthal plane. Therefore, xenon dynamic studies for AHWR with explicit xenon calculations were carried out using diffusion theory based computer code …

Transient Simulation Of Lbe Cooled Chtr Under Natural Circulation With 3d Multi-Physics Code Arch-Th, D. K. Dwivedi, Anurag Gupta, Umasankari Kannan

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

India is developing a 100kWth Compact High Temperature Reactor (CHTR) to facilitate demonstration of technologies for high temperature process heat applications. CHTR is being designed as thorium based TRISO fueled and beryllium oxide moderated prismatic block type vertical core cooled with lead-bismuth eutectic (LBE) under natural circulation for 1000°C outlet. The new concept of high temperature core requires multi-physics multi-scale modeling based tools for investigating the normal operational behavior as well as anticipated transients of CHTR. In view of that, 3D multi-physics code ARCH-TH is being indigenously developed and validated for coupled neutronics-thermal hydraulic benchmarks. The multi-group diffusion based neutron …

Flow And Thermal Effects Of Blockages In A Nano-Fluid Cooled Nuclear Fuel Subassembly, Shubham Mandot, N. Govindha Rasu

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Nanofluids have a great impact on heat transfer characteristics due to increased thermal conductivity and heat transfer coefficient. In this study, Titanium nanoparticles mixed in liquid sodium has been chosen for analyzing the effect of Nanofluid coolant for a Nuclear Sub- assembly. This study is conducted to observe the effect of nanoparticles on the flow properties and heat transfer characteristics such as velocity, heat transfer coefficient, clad temperature, coolant temperature etc. These effects have been observed for varying nanoparticle concentration and different flow blockage sizes. For this study, 7-pin fuel bundle with and without blockage has been modeled and analyzed …

Transient Analysis Of Primary Feed Pump Trip For 700 Mwe Iphwr, S. Phani Krishna, S. Pahari, S. Hajela, M. Singhal

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

700 MWe Indian Pressurized Heavy Water Reactor (IPHWR) is a horizontal channel type reactor with two loops of Primary Heat Transport (PHTS) system. Three (two operating and one stand by) main boiler feed water pumps (BFP) supply feed water to Steam Generators (SGs). In the event of one of the running BFP trip, standby comes on line on auto. Transient analysis for this event is performed using in- house computer code ATMIKA.T .The transient has been initiated by tripping one of the pumps.

Two cases are postulated:

1: BFP Trip and Standby BFP available on auto
2: BFP Trip and …

Heavy Water Concentration Measurement In Air, A. Gupta, D. V. Uduapa, A. Topkar, A. K. Mohanty

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

The heavy water in PHWRs flows at high temperature and pressure, hence leaks in the heat transport system are not uncommon. The loss of heavy water due to such leaks can lead to spreading of radioactivity and it also contributes to operating cost of the nuclear reactor. It is advantageous to detect small leaks, because if remains undetected, they may develop into a severe leak, which may lead to reactor shutdown. None of the sensors which are currently in use can meet all the requirement of high sensitivity, and real time measurement which is free from interference from other gamma …

Thermal Stratification In Liquid Metal Pools Under Cold Transients, Brendan Ward, Hitesh Bindra

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Experimental results are presented for understanding the thermal stratification or mixing in a low Prandtl number, Pr, pool due to the injection of a colder (higher density) jet at the bottom of the pool. In liquid metals (Pr<<1), the higher volumetric thermal expansion enhances buoyant forces, aiding in thermal stratification while the low Pr extends the thermal boundary layer. Rayleigh backscattering with swept wavelength interferometry is used to generate the high fidelity distributed temperature data. The high spatial and temporal resolution of the sensors are required to capture the temperature gradient and fluctuations of temperature allowing more …

Non-Optical Imaging Of Flow, Boiling, And Salt Deposition In A Simulated Debris Bed, Molly Ross, Alan Cebula, Steven Eckels, D. S. Mcgregor, Hitesh Bindra

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Determining flow and heat transfer characteristics in a debris bed or a packed bed is difficult due to the lack of optical access. Non-optical imaging methods, such as x-ray or neutron imaging, can be used to observe flow characteristics and particle deposition, as well as boiling in a packed bed. An amorphous Silicon detector based digital radiography camera can be used to image with either x-rays or neutrons at up to 100 frames per second. The digital radiography camera, coupled with digital image analysis techniques was used to characterize fluid fraction and flow rates in a simulated debris bed. A …

Enhancements To The Discrete Generalized Multigroup Method, R. L. Reed, J. A. Roberts

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

This work seeks to improve the practicality of the discrete generalized multigroup (DGM) method. The DGM method divides a fine-group energy domain into a set of coarse groups. Fine-group fluxes within each coarse group are expanded in an orthogonal basis, and cross section moments are defined to preserve the reaction rates of the fine-group solution. Previous implementations of DGM suffered from large memory requirements, so this work work explores options to reduce the memory footprint by (a) homogenizing cross-section moments over coarse regions and (b) representing discrete-angle dependence through truncated Legendre expansions. Tests were performed using a 1-D, discrete ordinates …

Matryoshka Inspired Statistical Surrogate For Turbulent Mixing, Abhinav Gairola, Hitesh Bindra

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Thermalhydraulics of reactor plena is often the most challenging problem due to turbulent mixing, role of jets and stratified flows. Due to which, the safety analysis of the overall reactor vessel or reactor system become complex. Inability of the system level analysis codes to accurately model the role of tur- bulent mixing in scalar transport leads to a major source of uncertainties. The computational cost of accurate CFD models renders the sensitivity studies using those for reactor safety ineffective. Reduced order models are needed which can effectively capture the effects of turbulent mixing and can be used for parametric studies …

Progress In Micro-Layered Fast Neutron Detectors, Priyarshini Ghosh, W. Fu, Mark J. Harrison, Patrick K. Doyle, Jeremy A. Roberts, D. S. Mcgregor

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

The study of accident tolerant fuels is ongoing at the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory. The TREAT Facility provides quick, high-energy neutron pulses that simulate various accident conditions. These neutron pulses are presently detected using an array of fast-neutron detectors called Hornyak buttons. Hornyak buttons suffer from poor detection efficiency and significant Ĉerenkov radiation contamination in the signal. A new enabling technology, the micro-layered fast-neutron detector (MLFD), is presented to monitor neutron flux changes during mild-to-severe reactor accidents. The MLFD was designed to overcome the shortcomings of the Hornyak buttons and to improve detection efficiency. The …

Numerical Evaluation Of Micro-Pocket Fission Detectors, Wenkai Fu, Daniel M. Nichols, Douglas S. Mcgregor, Jeremy A. Roberts

Symposium on Advanced Sensors and Modeling Techniques for Nuclear Reactor Safety

Micro-pocket fission detectors (MPFDs) are miniature fission chambers suitable for in-core neutron measurement that have been under development at Kansas State University for over one decade. Current-generation devices have been used at a number of university reactors (Kansas State, Wisconsin, and MIT) and as part of the first experiments performed during the recent restart of TREAT. Ongoing research aims to improve understanding of the existing MPFDs and to optimize designs for future deployment. To aid in this development, the dynamic response of a prototypic MPFD was evaluated using Garfield++, Elmer, Gmsh, and Stopping and Range of Ions in Matter (SRIM). …