Nuclear Engineering Commons^™

Accident Tolerant Fuels Claddings And The Evolution Of Their Surface Characteristics Under Critical Heat Flux, Rajnikant V. Umretiya

Theses and Dissertations

Enhanced Accident Tolerant Fuels (ATFs) systems for light water reactors require higher temperature oxidation resistance in steam environments than the current UO₂ – zirconium fuel system. Investigating the ATF materials’ surface properties is needed as they have evidenced to affect the Critical Heat Flux (CHF), which is an important parameter of the thermal-hydraulic performance required to provide safety margins. In this dissertation, the surface properties of FeCrAl alloys (APMT and C26M), Zircaloy-2, Zircaloy-4, and Cr-coating on Zircaloy-4 substrates produced by Physical Vapor Deposition (PVD) and Cold Spray (CS) were investigated according to their chemistry, topography, and wettability. The static …

Effect Of Dielectric Barrier Discharge Plasma Hydrogenation On Oxidation Stability Of Biodiesel Derived From Vegetable Oils, Grittima Kongprawes

Chulalongkorn University Theses and Dissertations (Chula ETD)

A parallel-plate type dielectric barrier discharge (DBD) plasma was utilized to produce partially hydrogenated fatty acids methyl ester (PH-FAME) derived from soybean and palm FAME. PH-FAME exhibits improved oxidation resistance, resulting in a longer storage time and a delay in changing fuel properties. The DBD plasma reaction occurred at atmospheric pressure and ambient temperature without a catalyst. The best condition for 35 mL of soybean FAME hydrogenation was using 25% H2 at ambient temperature for 5.5 h. An increase in saturated and monounsaturated FAMEs corresponded to a reduction of iodine value from 128 to 67.4. This condition created trans fatty …

Production Of Low Trans-Fatty Acid Margarine By Plasma Hydrogenation, Kunlanan Puprasit

Chulalongkorn University Theses and Dissertations (Chula ETD)

Margarine is a widely used raw material in the food and bakery industry. A successfully novel technique for refined palm olein hydrogenation to free trans-fat margarine production using non-thermal dielectric barrier discharge (DBD) plasma has been demonstrated. The new green method does not use chemicals as a catalyst, thus making it extremely environmentally friendly. This also performs well at room temperature and atmospheric pressure making it easier to manage. Two-electrode arrangement patterns were studied in this research: parallel plate and needle-in-tube. The results showed that using the parallel plate electrodes, 1.44% trans-fat (was detected) and a trans-fat generation rate of …

การคำนวณการรั่วไหลของสารประกอบซีเซียมในบ่อเก็บเชื้อเพลิงใช้แล้วของโรงไฟฟ้านิวเคลียร์ฟุกุชิมะไดอิจิหน่วยที่สี่ด้วยโปรแกรม Modified Art Mod 2, ชัยวิวัฒน์ กฤตสิน

Chulalongkorn University Theses and Dissertations (Chula ETD)

ในอุบัติเหตุร้ายแรงของโรงไฟฟ้าฟุกุชิมะไดอิจิที่ประเทศญี่ปุ่นในปี ค.ศ. 2011 อุบัติเหตุในบ่อเก็บเชื้อเพลิงใช้แล้วของโรงไฟฟ้าฟุกุชิมะไดอิจิหน่วยที่สี่ที่กักเก็บแท่งเชื้อเพลิงจำนวนมาก เป็นประเด็นสำคัญที่ผู้เชี่ยวชาญและนักวิจัยด้านความปลอดภัยทางนิวเคลียร์เล็งเห็นถึงความสำคัญของอุบัติเหตุร้ายแรงในบ่อเก็บเชื้อเพลิงใช้แล้ว ที่อาจส่งผลกระทบร้ายแรงเทียบเท่าหรือมากกว่าอุบัติเหตุร้ายแรงทางนิวเคลียร์จากการหลอมเหลวแท่งเชื้อเพลิงในเครื่องปฏิกรณ์นิวเคลียร์ สำหรับประเทศไทยงานวิจัยเกี่ยวกับอุบัติเหตุร้ายแรงของโรงไฟฟ้านิวเคลียร์ได้ถูกศึกษาและพัฒนาเพื่อส่งเสริมและสนับสนุนวางแผนการจัดการอุบัติเหตุทางนิวเคลียร์ และการวางแผนการรับมือผลกระทบทางนิวเคลียร์ จากโรงไฟฟ้านิวเคลียร์ที่อยู่ใกล้เคียงกับประเทศไทยและประเทศในภูมิภาคอาเซียน ดังนั้นความเข้าใจการดำเนินไปของอุบัติเหตุในบ่อเก็บเชื้อเพลิงใช้แล้วของโรงไฟฟ้าฟุกุชิมะไดอิจิ จึงเป็นอีกหนึ่งประเด็นวิจัยที่มีความจำเป็นต้องมีการศึกษาเพื่อนำข้อมูลไปใช้ในการวางแผนการรับมือผลกระทบทางนิวเคลียร์ที่อาจเกิดขึ้นได้ในอนาคต งานวิจัยนี้ศึกษาการเกิดอุบัติเหตุในกรณีสูญเสียอุปกรณ์ในการหล่อเย็นในบ่อเก็บเชื้อเพลิงของโรงไฟฟ้าฟุกุชิมะไดอิจิหน่วยที่สี่ โดยเริ่มจากกการประเมินความร้อนจากการสลายตัวของเชื้อเพลิงนิวเคลียร์โดยใช้แบบจำลองทางคณิตศาสตร์และสมการที่เกี่ยวข้องเมื่อเกิดอุบัติเหตุขึ้น เพื่อใช้ในการคำนวณอุณหภูมิของน้ำหล่อเย็นที่จะเพิ่มขึ้น และเวลาที่ใช้ในการทำให้น้ำหล่อเย็นในบ่อเก็บเชื้อเพลิงเกิดการเดือดและระเหย ตามลำดับ จากการคำนวณพบว่า ระดับน้ำหล่อเย็นจะลดลงจนถึงบริเวณส่วนบนของปลอกหุ้มเชื้อเพลิง เป็นเวลาประมาณ 14 วัน และส่วนล่างของปลอกหุ้มเชื้อเพลิง และ 30 วันตามลำดับ อุณหภูมิของปลอกหุ้มเชื้อเพลิงจะเพิ่มขึ้นจนถึง 1100 องศาเคลวิน ภายในเวลา 17 วัน โดยในระยะเวลาดังกล่าวคาดว่าทำให้เชื้อเพลิงนิวเคลียร์เกิดการบวมและแตกออกจากปฏิกิริยาออกซิเดชัน ตามลำดับ ส่งผลให้สารกัมมันตรังสีรั่วไหลออกไปสู่สิ่งแวดล้อม จากนั้นจึงใช้โปรแกรม Modified ART Mod 2 ในการจำลองการรั่วไหลของซีเซียมไอโดไดด์ในรูปแบบของแก๊สและซีเซียมไฮดรอกไซด์ในรูปแบบของแอโรซอลในขณะที่เกิดปฏิกิริยาออกซิเดชัน ซึ่งพบว่าซีเซียมไอโดด์ในรูปแบบของแก๊สและซีเซียมไฮดรอกไซด์ในรูปแบบของแอโรซอลสามารถรั่วไหลออกไปสู่สิ่งแวดล้อมอย่างมีนัยสำคัญ

การจำลองมอนติคาร์โลของการเกิดรังสีเอกซ์ในเครื่องพลาสมาโฟกัส, ภัคจิรา คชเสนี

Chulalongkorn University Theses and Dissertations (Chula ETD)

ในวิจัยนี้ได้ทำการจำลองการแผ่รังสีเอกซ์โดยใช้โมเดลจากเครื่องพลาสมาโฟกัส TPF – II ขนาด 1.5 kJ ด้วยโปรแกรมคอมพิวเตอร์แบบมอนติคาร์โล (Geant4) โดยทำการจำลองในช่วงที่เกิดอันตรกิริยาระหว่างลำอิเล็กตรอนกับขั้วแอโนดและทำการวิเคราะห์รังสีเอกซ์ที่เกิดขึ้น ทำการเปรียบเทียบรังสีเอกซ์เมื่อมีการเปลี่ยนลักษณะของขั้วแอโนดในส่วนของวัสดุและรูปร่างซึ่งได้แก่ 1. ขั้วแอโนดทรงกระบอกตันทำจากทองแดง 2. ขั้วแอโนดทรงกระบอกตันทำจากทังสเตน 3. ขั้วแอโนดทรงกระบอกเจาะรูทำจากทองแดง 4. ขั้วแอโนดทรงกระบอกเจาะรูทำจากทังสเตน โดยผลการจำลองพบว่าปริมาณรังสีเอกซ์จะมีค่าสูงสุดมุม 60-70 องศา เมื่อพลังงานของลำอิเล็กตรอนประมาณ 200 keV และที่มุม 10 องศา เมื่อพลังงานของลำอิเล็กตรอนตั้งแต่ 300 keV ขึ้น โดยวัสดุของขั้วแอโนดที่ให้ค่าปริมาณรังสีเอกซ์สูงสุด ได้แก่ ทังสเตน

Equations Of State For Warm Dense Carbon From Quantum Espresso, Derek J. Schauss

Theses and Dissertations

Warm dense plasma is the matter that exists, roughly, in the range of 10,000 to 10,000,000 Kelvin and has solid-like densities, typically between 0.1 and 10 grams per centimeter. Warm dense fluids like hydrogen, helium, and carbon are believed to make up the interiors of many planets, white dwarfs, and other stars in our universe. The existence of warm dense matter (WDM) on Earth, however, is very rare, as it can only be created with high-energy sources like a nuclear explosion. In such an event, theoretical and computational models that accurately predict the response of certain materials are thus very …

Surface Characterization Of Accident Tolerant Fuel Claddings Candidates After Prolonged Exposure To Steam Oxidation, Connor F. Donlan

Theses and Dissertations

Accident Tolerant Fuel Claddings are designed to improve fuel performance and safety in abnormal reactor conditions. The development of these cladding materials has become a top priority for the nuclear community, with incidents such as the Three Mile Island accident and the Fukashima Dai-chi accident. The development of these claddings has resulted in 2 subsections: coating current claddings or replacing cladding materials with new materials. The claddings studied in this thesis are a Zircaloy-4 cladding coated with chromium through physical vapor deposition, Zircaloy-4, and a FeCrAl alloy, C26M. This thesis assessed the surface chemistry, roughness, and wettability after extended exposure …

Development Of Complex Lattice Cell In Benchmark Model Of Particle Bed Critical System, Elijah Chamberlain Lutz

Masters Theses

“Criticality safety benchmark evaluations require the creation of models that most accurately represent the experiment being evaluated. In some cases this can be relatively trivial with experiments containing rather simple or standard geometry. In others, such as packed bed systems, this becomes unique and a more difficult process. The importance of accurate modeling of packed bed systems for the use of criticality safety benchmark evaluations was looked at. Four models were created of various complexities and accuracy. First the multi-particle bed, consisting of a fuel particle (UC_1.7 kernel with C shell) and two filler particles (Zircaloy-4 and C + …

Scaling, Experiments, And Simulations Of Condensation Heat Transfer For Advanced Nuclear Reactors Safety, Palash Kumar Bhowmik

Doctoral Dissertations

“The purpose of this research was to perform scaled experiments and simulations to validate computational fluid dynamics (CFD) and empirical models of condensation heat transfer (CHT) for the passive containment cooling system (PCCS) of Small Modular Reactors (SMRs). SMRs are the futuristic candidates for clean, economic, and safe energy generation; however, reactor licensing requires safety system evaluations, such as PCCS. The knowledge in the reviewed relevant literature showed a gap in experimental data for scaling SMR’s safety systems and validating computational models. The previously available test data were inconsistent due to unscaled geometric and varying physics conditions. These inconsistencies lead …

Effect Of Radiation Damage On Organic Phase Change Materials Thermal Storage Properties, Ryan Phillip Steere

Doctoral Dissertations

"This work discusses the effects of radiation damage on organic phase change materials for use in nuclear reactor containments and space craft. The effects of radiation on the latent heat of polyethylene wax (PEW) and a eutectic of methyl palmitate and lauric acid (EMPaLA) are evaluated. These PCMs were irradiated in three locations: the Missouri University of Science and Technology research reactor (MSTR), the University of Missouri research reactor (MURR) and cyclotron (MUC) up to a total dose of 2826, 2895 and 662 Gy, respectively. The samples irradiated at the MSTR showed latent heat changes up to 15.5% lower than …

Delayed Fast Neutron As An Indicator Of Burn-Up For Nuclear Fuel Elements, Tayfun Akyurek, Shoaib Usman, S. B. Shoaib

Nuclear Engineering and Radiation Science Faculty Research & Creative Works

Feasibility study of burn-up analysis and monitoring using delayed fast neutrons was investigated at Missouri University of Science and Technology Reactor (MSTR). Burnt and fresh fuel elements were used to collect delayed fast neutron data for different power levels. Total reactivity varied depending on the burn-up rate of fuel elements for each core configuration. The regulating rod worth was 2.07E-04 Δk/k/in and 1.95E-04 Δk/k/in for T121 and T122 core configurations at 11 inch, respectively. Delayed fast neutron spectrum of F1 (burnt) and F16 (fresh) fuel elements were analyzed further, and a strong correlation was observed between delayed fast neutron emission …

Impact Of Neutron Energy On Asteroid Deflection Performance, Lansing S. Horan Iv, Darren E. Holland, Megan Bruck Syal, James E. Bevins, Joseph W. Wasem

Faculty Publications

In the future, a hazardous asteroid will find itself on a collision course with Earth. For asteroids of moderate size or larger, a nuclear device is one of humanity's only technologies capable of mitigating this threat via deflection on a timescale of less than a decade. This work examined how the output neutron energy from a nuclear device standoff detonation affects the deflection of a notional asteroid that is 300 meters in diameter and composed of silicon dioxide at a bulk density of 1.855 g/cm³. 14.1 MeV and 1 MeV neutron energy sources were modeled in MCNP to …

Deconvolution Of Mono-Energetic And Multi-Lines Gamma-Ray Spectra Obtained With Nai(Tl) Scintillation Detectors Using Direct Matrix Inversion Method, Mwingereza John Kumwenda Dr

Tanzania Journal of Engineering and Technology (TJET)

Performance of a NaI(Tl) scintillation detector based on the gamma-ray spectroscopy system is not satisfactory in retaining its original peak (which is delta like function) of various gamma ray spectrum. The method of achieving precise peak for the various gamma ray was conducted by converting the observed pulse-height distribution of the NaI(Tl) detector to a true photon spectrum. This method is obtained experimentally with the help of an inverse matrix deconvolution method. The method is based on response matrix generated by the Monte Carlo simulation based on Geant4 package of mono-energy gamma-ray photon ranging from 0.050 to 2.04 MeV in …

Small Modular Reactors And Advanced Reactor Security: Regulatory Perspectives On Integrating Physical And Cyber Security By Design To Protect Against Malicious Acts And Evolving Threats, Raphael Duguay

International Journal of Nuclear Security

How can future nuclear technologies and Small Modular Reactors (SMRs) deter and prevent organized crime groups, terrorists, and malicious actors from attempting to steal or sabotage nuclear materials and facilities? This paper presents the benefits of integrating Security by Design (SeBD) into a regulatory framework to allow more a flexible and effective design of physical protection systems for SMRs. During its effort to modernize the Nuclear Security Regulations, the Canadian Nuclear Safety Commission (CNSC) licensing application process provides for the option of SeBD in moving toward a performance-based approach with less prescriptive requirements. CNSC also recognizes the need for a …

Fast Neutron Assay Of Elemental Content Of Bulk Samples, Calder Emerson Lane

UNLV Theses, Dissertations, Professional Papers, and Capstones

The purpose of this research was to analyze the capabilities of fast neutrons in the detection and analysis of various isotopes in bulk samples. The deuterium-tritium (DT) fusion reaction generates highly penetrating, high-energy (14.1-MeV) neutrons which induce nuclear reactions in irradiated targets. Neutrons and gamma rays are generated in these reactions. Emitted gamma rays are characteristic of the emitter; the gamma spectrum enables stoichiometric identification of the assayed samples. Neutron backscattering can also be used for identification of the elemental composition of the sample.

This work had three objectives. The first objective was to develop a computational technique to model …

Experimental Evaluation Of The Deadtime Phenomenon For Gm Detector: Deadtime Dependence On Operating Voltages, Bader Almutairi, Syed B. Alam, Tayfun Akyurek, Cameron S. Goodwin, Shoaib Usman

Nuclear Engineering and Radiation Science Faculty Research & Creative Works

A detailed analysis of Geiger Mueller counter deadtime dependence on operating voltage is presented in the manuscript using four pairs of radiation sources. Based on two-source method, detector deadtime is calculated for a wide range of operating voltages which revealed a peculiar relationship between the operating voltage and the detector deadtime. In the low voltage range, a distinct drop in deadtime was observed where deadtime reached a value as low as a few microseconds (22 µs for ²⁰⁴Tl, 26 µs for ¹³⁷Cs, 9 µs for ²²Na). This sharp drop in the deadtime is possibly due to reduced …

A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code For Atmospheric Particle Transport, Daniel T. Wakeford

Nuclear Engineering ETDs

A natural coordinate system for calculating neutral particle propagation in the atmosphere due to point sources is two-dimensional spherical-polar coordinates. Deterministic methods for solving the transport equation in this coordinate system require some interesting implementation details stemming from the two angular derivatives present in this form of the equation. In this dissertation, we present a bilinear discontinuous spatial discretization of the transport equation in this coordinate system. The weighted diamond difference discretization is applied to the angular derivative term in two angular dimensions, using zero-weighted starting directions to start the differencing. To our knowledge, the only previous deterministic code that …

Computational Modeling Of Radiation Damage In A Multi-Phase Ceramic Waste Form Using Moose, Zeyu Chen

Theses and Dissertations

Ceramic waste forms have been proposed to replace the traditional glassy waste forms for long term stabilization of radionuclides. These waste forms are constantly exposed to self-irradiation emitted from the constituent radionuclides causing their material properties to change accordingly. It has been known that the radiation damage in waste forms is dominated by alpha particles emitted from transuranic (TRU) radionuclides. Since alpha particles usually have a range of 10~20 μm in such waste forms, some fraction of any non-transuranic containing phases (for a multiphase waste form) will be undamaged (or less damaged) if containing large enough grain sizes. Modeling and …

Corrigendum: “A Correlation For Interfacial Area Concentration In High Void Fraction Flows In Large Diameter Channels” ([Chem. Eng. Sci.131 (2015) 172–186] (2015) 131 (172–186), (S0009250915002547), (10.1016/J.Ces.2015.04.004)), Joshua P. Schlegel, T. Hibiki

Nuclear Engineering and Radiation Science Faculty Research & Creative Works

There is a Typographical Mistake in Eq. (21), Used in the Derivation of the Final Model, Which Should Read [Fourmula Presented] This Typographical Mistake is Also Present in Eq. (22b), Which is Necessary for Implementation of the Final Model, Which Should Read

A 3d Image-Guided System To Improve Myocardial Revascularization Decision-Making For Patients With Coronary Artery Disease, Haipeng Tang

Dissertations

OBJECTIVES. Coronary artery disease (CAD) is the most common type of heart disease and kills over 360,000 people a year in the United States. Myocardial revascularization (MR) is a standard interventional treatment for patients with stable CAD. Fluoroscopy angiography is real-time anatomical imaging and routinely used to guide MR by visually estimating the percent stenosis of coronary arteries. However, a lot of patients do not benefit from the anatomical information-guided MR without functional testing. Single-photon emission computed tomography (SPECT) myocardial perfusion imaging (MPI) is a widely used functional testing for CAD evaluation but limits to the absence of anatomical information. …

Characterization Of Partial Charge Collection Induced By Neutron Damage In High-Purity Germanium Detectors, James W. Evans

Nuclear Engineering ETDs

This paper investigates the correlation of damage induced by neutron interactions and degradation in the spectra of HPGe detectors. As neutrons kinetically interact with germanium crystals, they create interstitial and vacancy defects within the lattice. These defects then interfere with the charge migration of electron-hole pairs and reduce resolution in the observed energy spectrum. The partial charge collection produces observable spectral changes by increasing the peak width and reducing resolution (full width half maximum). A detailed characterization using various check sources was performed before and after iterations of neutron exposure in order to observe the effects of the neutron damage. …

Promoting Nuclear Security Education And Training Activities At Amity University, India, Arpita Datta, Dr. Alpana Goel

International Journal of Nuclear Security

In the present era of global nuclear governance, it is the responsibility of every individual not only the security personals to be accountable for the security of nuclear materials, facilities and radioactive materials. Amity university and other universities of India are the largest educational networks for young professionals who will enter the nuclear programme in India and will be involved in the management of nuclear and other radioactive materials in a wide variety of applications such as hospitals, industrial applications and nuclear facilities. Amity University Uttar Pradesh is taking leading part to sensitize the importance of nuclear security amongst the …

Eusectra: European Nuclear Security Training Centre Providing Hands-On Training And Education In Nuclear Security And Safeguards, Willem Janssens, Veronique Berthou, Abbas Kamel, Jean Galy, Klaus Luetzenkirchen, Klaus Mayer, Stefan Nonneman

International Journal of Nuclear Security

The European Nuclear Security Training Centre (EUSECTRA) inaugurated under this global name about 10 years ago and operated by the European Commission Joint Research Centre (JRC), located both on the Karlsruhe (Germany) and Ispra (Italy) sites, includes a large variety of capacity building and professional development activities which span from the hands-on training for nuclear security and safeguards actors (e.g. respectively border guards or customs and nuclear inspectors) to educational efforts in both nuclear security and safeguards. Whereas the first ones, which gave rise to the new name, focus mainly on detection, on-site assistance, crime-scene management, technical reach-back and nuclear …

Parking Garage Measurements Indicating A Gamma Spectrometer-Neutron Counter Background Correlation, Jackson N. Wagner, Craig Marianno, Thomas Mccullough

International Journal of Nuclear Security

Gamma spectroscopy and gross neutron counting systems are commonly employed together during nuclear security operations, particularly mobile searches. The data from these systems are typically analyzed independently; however, operational data suggest a relationship between the background signals from both systems. This relationship appears to occur between the neutron count rate and the high energy (greater than 3 MeV) gamma spectrometer count rate for background conditions. To verify the presence of this correlation, high energy gamma ray and neutron count rates were measured in five parking garages on the Texas A&M University campus. These measurements employed one 4” x 4” x …

Consideration Of Administrative Monetary Penalties In Nuclear Safety And Security, Jelena Vucicevic, Edward Waller

International Journal of Nuclear Security

An Administrative Monetary Penalty (AMP) is a penalty imposed by the Canadian Nuclear Safety Commission (CNSC), without court involvement for a violation of a regulatory requirement. An AMP can be applied against any individual or corporation subject to the Nuclear Safety Control Act, which regulates the development, production and use of nuclear energy and the production, possession and use of nuclear and radioactive material. However, AMPs are not the same as criminal offences. They are civil sanctions which try to secure compliance through the application of monetary penalties for non-compliance with regulatory requirements. The AMP program was introduced in 2013 …

Applications Of Portable Libs For Actinide Analysis, Ashwin P. Rao, John D. Auxier Ii, Dung Vu, Michael B. Shattan

Faculty Publications

A portable LIBS device was used for rapid elemental impurity analysis of plutonium alloys. This device demonstrates the potential for fast, accurate in-situ chemical analysis and could significantly reduce the fabrication time of plutonium alloys.

A Physics-Based Machine Learning Study Of The Behavior Of Interstitial Helium In Single Crystal W–Mo Binary Alloys, Adib J. Samin

Faculty Publications

In this work, the behavior of dilute interstitial helium in W–Mo binary alloys was explored through the application of a first principles-informed neural network (NN) in order to study the early stages of helium-induced damage and inform the design of next generation materials for fusion reactors. The neural network (NN) was trained using a database of 120 density functional theory (DFT) calculations on the alloy. The DFT database of computed solution energies showed a linear dependence on the composition of the first nearest neighbor metallic shell. This NN was then employed in a kinetic Monte Carlo simulation, which took into …

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. …

Gen-Foam Multiphysics Model Development For Molten Salt Reactors, Jeffrey Stewart

UNLV Theses, Dissertations, Professional Papers, and Capstones

In thermal neutron spectrum Molten Salt Reactors (MSR), a graphite moderator contributes a positive reactivity value to the overall temperature reactivity coefficient of the core. When irradiated in the core, graphite undergoes dimensional changes which depend on the neutron spectrum. The graphite lifespan is a limiting parameter in MSR designs; it correlates strongly with the graphite’s dimensional changes. Multi-physics modeling is necessary to evaluate the graphite thermal and mechanical responses to the MSR core conditions. To assess graphite dimensional changes associated with irradiation, a computational model was developed upon the foundation of the multi-physics solver, GeN-Foam. Irradiated graphite dimensional change …

Remote Radiation Sensing Using Robotic Platforms, Monia Kazemeini

UNLV Theses, Dissertations, Professional Papers, and Capstones

Remote sensing of ionizing radiation has a significant role in waste management, nuclear material management and nonproliferation, radiation safety, and accident response in situations such as the Fukushima nuclear power plant accident. Robotic platforms are able to surpass the number of tasks that could be achieved by humans. With the use of robots, the operator’s radiation exposure can be considerably decreased. Remote sensing allows for the evaluation and monitoring of radiological contamination in hazardous and hard to reach areas and locating radiation sources. In this work, gamma-ray and neutron sensors were integrated onto the unmanned aerial systems (UAS) making it …