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Texas A&M University
1.
Fullerton, Christopher Todd.
Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.
Degree: MS, Nuclear Engineering, 2017, Texas A&M University
URL: http://hdl.handle.net/1969.1/165685
► In the event that a nuclear core cooling pipe ruptures, a loss of coolant accident (LOCA) scenario begins. Precipitates from dissolved ions can form and…
(more)
▼ In the event that a nuclear core cooling pipe ruptures, a loss of coolant accident (LOCA) scenario begins. Precipitates from dissolved ions can form and cause the emergency backup pumps to fail. Two aluminum products, an aluminum oxyhydroxide (AlOOH) and aluminum oxide solid are expected to have the greatest impact on debris bed formation. The objective of this experimental study was to classify these compounds by size, structure, and behavioral characteristics, and compare them to a benchtop salt generated precipitate made with aluminum nitrate nonahydrate. The source of the aluminum ions varies by plant, but they typically originate from corrosion of structures in the reactor containment environment. Characterizing the aluminum corrosion product is necessary to determine if an aluminum surrogate salt precipitate product can be substituted in the Nuclear Regulatory Commission’s (NRC) generic safety issue-191 (GSI-191) head loss testing to simplify testing procedures. If the surrogate salt product is comparable to the alloy corrosion product, it will simplify the task of studying sump strainer debris bed formation in future testing.
The representative post LOCA coolant solution for this experimental study was created at varying pH’s representative of containment chemistry. Aluminum samples were corroded at 85℃ ± 2℃ until the solubility limit was reached. The aluminum source was removed and the solution was cooled to 25℃ at three different cooling rates. The resulting solution was analyzed for turbidity, particle size, TEM, XRD, and settling characteristics. These results are compared to an aluminum nitrate nonahydrate surrogate salt precipitate prepared according to industry standards and regulations. The characterization of the precipitates proved to be dependent on corrosion pH, aluminum ion concentration, and cooling rate. The cooling rate dynamics indicate a higher probability of large precipitate formation during slow cooling rates and smaller particle formation during rapid cooling rates. The quantity of particles generated was assessed with solution turbidity. The solutions with higher concentrations of aluminum ions resulted in higher solution turbidity. The AlOOH precipitates from the Al(NO3)3·9H2O salt solution were determined to be a suitable substitute for further head loss testing in the chemical GSI-191 project.
Advisors/Committee Members: Hassan, Yassin A (advisor), Vaghetto, Rodolfo (advisor), King, Maria (committee member).
Subjects/Keywords: GSI-191; Alumina; Corrosion; Sodium Tetraborate (NaTB); Loss of Coolant Accident (LOCA); PWR; BWR
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APA (6th Edition):
Fullerton, C. T. (2017). Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/165685
Chicago Manual of Style (16th Edition):
Fullerton, Christopher Todd. “Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.” 2017. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/165685.
MLA Handbook (7th Edition):
Fullerton, Christopher Todd. “Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.” 2017. Web. 05 Mar 2021.
Vancouver:
Fullerton CT. Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. [Internet] [Masters thesis]. Texas A&M University; 2017. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/165685.
Council of Science Editors:
Fullerton CT. Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. [Masters Thesis]. Texas A&M University; 2017. Available from: http://hdl.handle.net/1969.1/165685

Texas A&M University
2.
Neptune, Kaleb Todd.
THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.
Degree: MS, Nuclear Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/174119
► In this study, the metazoan parasites of three species of freshwater turtles (the spiny softshell, Apalone spinifera, the common snapping turtle, Chelydra serpentina, and the…
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▼ In this study, the metazoan parasites of three species of freshwater turtles (the spiny softshell, Apalone spinifera, the common snapping turtle, Chelydra serpentina, and the red-eared slider, Trachemys scripta elegans) were surveyed at 16 sites across the state of
Texas. A total of 42 species of metazoan parasites were recovered from 15 A. spinifera, nine C. serpentina, and 55 T. s. elegans, representing 16 new host-parasite associations and 17 new locality records. The synonymy of Acanthostomum nuevoleonensis by Brooks (1980) is refuted and the species is redescribed. Two new species of monogenean worms in the genus Neopolystoma are reported, one from C. serpentina and A. spinifera and another from T. s. elegans. Through non-metric multidimensional scaling and analysis of similarities, A. spinifera was found to contain a significantly distinct parasite community from C. serpentina and T. s. elegans. A range of water parameters (ammonia, carbon dioxide, chloride, dissolved oxygen, hardness, nitrite, nitrate, pH, salinity, temperature, and turbidity) were recorded on each sampling trip and compared to parasite abundance and diversity. Ammonia levels were positively correlated with abundance of acanthocephalans. Carbon dioxide levels were negatively correlated with parasite diversity and monogenean abundance. Chloride levels were negatively correlated with parasite diversity. Dissolved oxygen levels were positively correlated with parasite diversity and monogenean abundance. Turbidity was positively correlated with parasite abundance, acanthocephalan abundance, and digenean abundance, and negatively correlated with parasite diversity. Parasite abundance was significantly lower in west
Texas and western river basins, and lower in rivers than ponds. Acanthocephalan abundance was significantly lower in rivers than ponds. Leech abundance was highest in the Trinity river basin. Turbidity had the strongest correlations in this study. As water clarity increased, diversity increased and abundance of certain taxa decreased, indicating clearer water may have greater food web diversity and healthier hosts. This study adds valuable data on host-parasite associations, parasite distributions, and parasite ecology of turtles in the state of
Texas. Many of these findings are likely transferable to other host taxa and should be studied in greater depth. Parasite diversity is not well known, even in common species, highlighting the need for more diversity surveys.
Advisors/Committee Members: Hassan, Yassin A (advisor), Vaghetto, Rodolfo (advisor), King, Maria (committee member).
Subjects/Keywords: BISON; RELAP5-3D; FRAPCON
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APA (6th Edition):
Neptune, K. T. (2018). THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174119
Chicago Manual of Style (16th Edition):
Neptune, Kaleb Todd. “THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.” 2018. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/174119.
MLA Handbook (7th Edition):
Neptune, Kaleb Todd. “THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS.” 2018. Web. 05 Mar 2021.
Vancouver:
Neptune KT. THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/174119.
Council of Science Editors:
Neptune KT. THERMAL-HYDRAULIC AND FUEL PERFORMANCE CODE COUPLING FOR MULTI-PHYSICS INDUSTRIAL APPLICATIONS. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174119

Texas A&M University
3.
Reyes, Denny L.
Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry.
Degree: MS, Mechanical Engineering, 2013, Texas A&M University
URL: http://hdl.handle.net/1969.1/151280
► In a pressurized water reactor (PWR), pressurized water flows over fuel rods containing radioactive uranium. Potential failure of these nuclear fuel rods is a primary…
(more)
▼ In a pressurized water reactor (PWR), pressurized water flows over fuel rods containing radioactive uranium. Potential failure of these nuclear fuel rods is a primary concern, as fuel rod failure typically results in power generation losses and reactor downtime. Thermal parameters such as critical heat flux have traditionally been utilized as performance metrics to ensure that the reactor core remains stable even during failure events. Recently, fuel leaking events have occurred which have resulted in excess debris buildup on fuel rods and fuel grid array mixing devices. Understanding the flow field surrounding these nuclear fuel rods is critical in predicting where crud could deposit. Although CFD simulations have been conducted to characterize the fluid flow around fuel rod bundles, limited experimental data characterizing the mechanics of this fluid flow exists in the current literature.
This study will present experimental data collected detailing the fluid flow around a rod bundle geometry using a novel matched refractive index particle tracking velocimetry (PTV) technique over a 3D volume cross section of a prototypical nuclear fuel rod bundle. Velocimetry tracking will be performed in order to characterize the mechanics of the fluid flow. Using optical distortion mitigation techniques and various image processing methods, data from multiple cameras was used to assemble 3-dimensional velocity information of a turbulent fluid region. Results are compared to the solution of a k-epsilon unsteady RANS numerical simulation.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H (committee member), Ranjan, Devesh (committee member).
Subjects/Keywords: PTV; particle tracking velocimetry; rod bundle
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APA (6th Edition):
Reyes, D. L. (2013). Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151280
Chicago Manual of Style (16th Edition):
Reyes, Denny L. “Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry.” 2013. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/151280.
MLA Handbook (7th Edition):
Reyes, Denny L. “Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry.” 2013. Web. 05 Mar 2021.
Vancouver:
Reyes DL. Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/151280.
Council of Science Editors:
Reyes DL. Three-Dimensional Velocity Measurement Reconstruction for a Rod Bundle Array using Matched Refractive Index Particle Tracking Velocimetry. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151280

Texas A&M University
4.
Cevik, Muhammet.
Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow.
Degree: MS, Mechanical Engineering, 2013, Texas A&M University
URL: http://hdl.handle.net/1969.1/151651
► The performance of a coupled slotted orifice and swirl flow meters, and a coupled slotted orifice and an impedance probe flow meter for multiphase flow…
(more)
▼ The performance of a coupled slotted orifice and swirl flow meters, and a coupled slotted orifice and an impedance probe flow meter for multiphase flow is evaluated to develop a new multiphase flow meter. The slotted orifice also provides well homogenized flow for several pipe diameters downstream of the plate. This characteristic provides a homogeneous mixture at the inlet of the swirl meter, and impedance probe for gas volume fraction measurement (GVF). In order to evaluate the performance of the designed flow<meters, the GVF and mass flow rate responses are investigated at varying pressures (20, 40, and 60 psi) and water flow rates (30, 40, 50, 60, 70, 80, and 90 GPM). The proper correlations are established to provide high accurate two<phase flow measurement. The new proposed approach provides the GVF measurement with less than 0.017 % error, and the total mass flow rate measurement within error ± 0.
38 over the range of 4 to 13 lbm/sec.
Advisors/Committee Members: Morrison, Gerald (advisor), Pate, Michael (committee member), Hassan, Yassin A. (committee member).
Subjects/Keywords: multiphase flow meter; slotted plate; swirl-meter; electrical impedance probe
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❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Cevik, M. (2013). Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151651
Chicago Manual of Style (16th Edition):
Cevik, Muhammet. “Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow.” 2013. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/151651.
MLA Handbook (7th Edition):
Cevik, Muhammet. “Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow.” 2013. Web. 05 Mar 2021.
Vancouver:
Cevik M. Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/151651.
Council of Science Editors:
Cevik M. Evaluation of a Close Coupled Slotted Orifice, Electrical Impedance, and Swirl Flow Meters for Multiphase Flow. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151651

Texas A&M University
5.
Lee, Hao-En.
Effects of Confined Structures on Pool Boiling Heat Transfer.
Degree: MS, Mechanical Engineering, 2016, Texas A&M University
URL: http://hdl.handle.net/1969.1/187420
► Pool boiling heat transfer is one of the most effective heat transfer processes used in a host of applications. The enhancement of pool boiling has…
(more)
▼ Pool boiling heat transfer is one of the most effective heat transfer processes used in a host of applications. The enhancement of pool boiling has been studied for decades by considering a variety of surface modifications and configurations. For that reason, this study investigates the effects of the confined structures on the pool boiling heat transfer. The confined structures consist of flanges, a plate with a central orifice and a mesh with a central orifice. The diameters of the plate orifice are 2 and 4 mm; the diameter of the mesh orifice size are 2.5, 3.5, 4.5 mm. By comparing the boiling curves of different confined structures, the effects of confinement on heat transfer performance can be evaluated. An infrared camera and a high speed camera were used to capture bubble images and for measuring surface temperature. Furthermore, a pump assisted system was used to determine the effect of confinement on vapor quality and system pressure.
The test results show that pool boiling heat transfer can be generally enhanced by using confined structures. The level of enhancement depends on the orifice size of the plate and the mesh. Smaller orifice size leads to higher heat transfer enhancement. The results of the pump assisted test indicate that the boiling heat transfer enhancement can be attributed to the bubble coalescence process and the induced shear flow caused by the coalesced bubble departure. Results also indicate than an increase of vapor generation (quality) and the induced shear flow rate (shear stress) can be found when increasing the level of confinement on the pool boiling process. Furthermore, using a mesh in confined structure can provide a higher heat transfer coefficient when compared to the no-mesh cases when a pump is used to facilitate bubble departure. In summary, the results show that using meshes leads to better heat transfer performance, which cannot be replicated using a solid surface as confinement structure.
Advisors/Committee Members: Alvarado, Jorge L. (advisor), Hassan, Yassin A. (committee member), Lee, Sungyon (committee member).
Subjects/Keywords: confined pool boiling; pool boiling
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APA ·
Chicago ·
MLA ·
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CSE |
Export
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APA (6th Edition):
Lee, H. (2016). Effects of Confined Structures on Pool Boiling Heat Transfer. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/187420
Chicago Manual of Style (16th Edition):
Lee, Hao-En. “Effects of Confined Structures on Pool Boiling Heat Transfer.” 2016. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/187420.
MLA Handbook (7th Edition):
Lee, Hao-En. “Effects of Confined Structures on Pool Boiling Heat Transfer.” 2016. Web. 05 Mar 2021.
Vancouver:
Lee H. Effects of Confined Structures on Pool Boiling Heat Transfer. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/187420.
Council of Science Editors:
Lee H. Effects of Confined Structures on Pool Boiling Heat Transfer. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/187420

Texas A&M University
6.
Ullah, Izhar.
Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.
Degree: MS, Mechanical Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/173881
► This thesis is an experimental study to examine the effect of different hole shapes and coolant hole trajectory on film cooling effectiveness and discharge coefficient.…
(more)
▼ This thesis is an experimental study to examine the effect of different hole shapes and coolant hole trajectory on film cooling effectiveness and discharge coefficient. PSP technique was used to calculate the film cooling effectiveness and film cooling contours. Effect of hole geometry and trajectory was studied at different density ratios and different blowing ratios. Three different density ratios DR=1, DR=1.5 and DR = 2 were used and five blowing ratios from
M= 0.5 - 1.5 were used with an increment of 0.25. Diameter of the hole was taken as 4 mm. Three different exit geometries (Round to slot-, Round to annulus, Round to annulus2) were used with linear and projectile trajectories, thus making a total of six test plates.
Results obtained agreed with the general trend of shaped holes. It is interesting to observe that slot shaped exit hole is still a better option than annulus shaped holes. Slot shaped exit hole with projectile trajectory resulted in improved effectiveness with 30-40% increase in span wise effectiveness as compared to its linear slot shaped counterpart. This improved design at DR=2 which corresponds to the actual conditions of a real engine. However round to slot test plate with projectile trajectory has the lowest discharge coefficient implying more pressure requirement for the coolant at the same blowing ratio. Correlation was obtained for a single row different exit shaped holes.
Advisors/Committee Members: Han, Je-Chin (advisor), Hassan, Yassin A. (committee member), Pate, Michael (committee member).
Subjects/Keywords: Film cooling; Pressure sensitive paint (PSP)
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APA ·
Chicago ·
MLA ·
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CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Ullah, I. (2018). Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173881
Chicago Manual of Style (16th Edition):
Ullah, Izhar. “Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.” 2018. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/173881.
MLA Handbook (7th Edition):
Ullah, Izhar. “Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.” 2018. Web. 05 Mar 2021.
Vancouver:
Ullah I. Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/173881.
Council of Science Editors:
Ullah I. Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173881

Texas A&M University
7.
Kappes, Ethan Daniel.
Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction.
Degree: MS, Nuclear Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/174370
► Randomly packed pebble bed structures are found in many engineering applications, such as solar thermal batteries, chemical catalytic reactors, fluid refinement and filtering, magnetic refrigerators,…
(more)
▼ Randomly packed pebble bed structures are found in many engineering applications, such as solar thermal batteries, chemical catalytic reactors, fluid refinement and filtering, magnetic refrigerators, biological tissues, and pebble bed reactors. The critical challenge of designing and analyzing a packed bed structure especially in the nuclear industry comes from its complex and dynamic geometry. Modeling and understanding the complex flow, heat and mass transfer, and vorticity phenomena within the bed on a micro scale involves in-depth analysis of the interstitial regions that make up its entirety. Unfortunately, complex geometries and randomly connected void spaces within packed beds have hindered efforts to characterize the underlying transport phenomena.
Current research lacks analysis and validation against accurate computational fluid dynamics models for randomly packed structures. This lack of understanding prevents proper leveraging of the pebble bed reactor’s passive safety features. Current PIV research that involves randomly packed structures does not also provide a 3-Dimensional (3D) replica of the test bed for verification. Noninvasive measurements coupled with a full 3D test bed replica for computational fluid dynamic verification and validation will lead to a full understanding of the microscopic flow phenomena within pebble bed reactors.
Texas A&
M University is conducting isothermal experiments of pressure drops, and flow analysis in a randomly packed pebble bed experimental facility to support the research on advanced nuclear reactors. The data collected is expected to be suitable for computational fluid dynamics validation. The design, construction, and collection of shakedown pressure and PIV data with differing pebble to pipe diameter ratios were conducted in efforts to provide needed data on local flow measurements. The use of nonintrusive PIV analysis on a randomly matched index of refraction facility. This approach allows for a non-invasive probe into the flow within packed spheres at the microscopic scales with high temporal and spatial resolutions. Effects of the wall boundary and Reynolds on flow characteristics obtained from the TR-PIV measurements with are presented with high spatial and temporal resolution.
Advisors/Committee Members: Hassan, Yassin A (advisor), Vaghetto, Rodolfo (committee member), King, Marie (committee member).
Subjects/Keywords: Pebble Bed Reactor; PIV; MIR; Packed Bed
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APA ·
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MLA ·
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APA (6th Edition):
Kappes, E. D. (2018). Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174370
Chicago Manual of Style (16th Edition):
Kappes, Ethan Daniel. “Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction.” 2018. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/174370.
MLA Handbook (7th Edition):
Kappes, Ethan Daniel. “Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction.” 2018. Web. 05 Mar 2021.
Vancouver:
Kappes ED. Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/174370.
Council of Science Editors:
Kappes ED. Design, Development, and Execution of PIV Measurements on a Randomly Packed Pebble Bed Experimental Facility Using Matched Index of Refraction. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174370

Texas A&M University
8.
Gaskill, Travis.
Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry.
Degree: MS, Mechanical Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10585
► The present study has focused on the use of coil heat exchangers (CHEs) with microencapsulated phase change material (MPCM) slurries to understand if CHEs can…
(more)
▼ The present study has focused on the use of coil heat exchangers (CHEs) with microencapsulated phase change material (MPCM) slurries to understand if CHEs can yield greater rates of heat transfer. An experimental study was conducted using a counterflow CHE consisting of 3 helical coils. Two separate tests were conducted, one where water was used as heat transfer fluid (HTF) on the coil and shell sides, respectively; while the second one made use of MPCM slurry and water on the coil and shell sides, respectively. The NTU-effectiveness relationship of the CHE when MPCM fluid is used approaches that of a heat exchanger with a heat capacity ratio of zero. The heat transfer results have shown that when using a MPCM slurry, an increase in heat transfer rate can be obtained when compared to heat transfer results obtained using straight heat transfer sections. It has been concluded that the increased specific heat of the slurry as well as the fluid dynamics in helical coil pipes are the main contributors to the increased heat transfer.
Advisors/Committee Members: Alvarado, Jorge L. (advisor), Hassan, Yassin A. (committee member), Banerjee, Debjyoti (committee member).
Subjects/Keywords: Heat Transfer; Heat Exchanger; Helical Coil; Microencapsulated Phase Change Material
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Gaskill, T. (2012). Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10585
Chicago Manual of Style (16th Edition):
Gaskill, Travis. “Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10585.
MLA Handbook (7th Edition):
Gaskill, Travis. “Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry.” 2012. Web. 05 Mar 2021.
Vancouver:
Gaskill T. Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10585.
Council of Science Editors:
Gaskill T. Heat Transfer of a Multiple Helical Coil Heat Exchanger Using a Microencapsulated Phase Change Material Slurry. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10585

Texas A&M University
9.
Cook, William McKinley.
Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.
Degree: MS, Nuclear Engineering, 2014, Texas A&M University
URL: http://hdl.handle.net/1969.1/158626
► This thesis work involves the use of the RELAP5-3D thermal hydraulic code to model flow for a typical pressurized water reactor (PWR). A model using…
(more)
▼ This thesis work involves the use of the RELAP5-3D thermal hydraulic code to model flow for a typical pressurized water reactor (PWR). A model using several three-dimensional components was created to accurately predict complex accident scenarios with greater fidelity and detail than models consisting of only one-dimensional control volumes. In order to build this model, a one-dimensional model was first used as a reference and a foundation. The three-dimensional model was then constructed from this reference model using various techniques and methodologies. These are described in this thesis and represent best practices for similar work. Additionally, a tool was constructed to enhance the ease and accuracy of utilizing both Cartesian and cylindrical components. An overview of this tool is presented in this thesis, which includes verification and validation efforts as well as a discussion on its capabilities and use. After the three-dimensional model had been finalized, it was compared to its one dimensional analogue using a variety of metrics that demonstrate its consistency with the one dimensional reference. A detailed summary of this comparison is presented in this work. The final model was developed for use in Loss-of-Coolant Accident (LOCA) scenarios that simulate hypothesized situations relating to the Nuclear Regulatory Commission’s (NRC’s) Generic Safety Issue 191 (GSI-191). Thus, a standard of prudence was implemented (i.e. specifications) to ensure the model would be capable of accurately predicting phenomena associated with such scenarios.
Advisors/Committee Members: Hassan, Yassin A (advisor), King, Maria (committee member), Marlow, William H (committee member).
Subjects/Keywords: RELAP; RELAP5-3D; PWR; GSI-191; Three-Dimensional Nodalization; LOCA; Thermal Hydraulics; Nuclear Reactor; Safety Analysis
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APA (6th Edition):
Cook, W. M. (2014). Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158626
Chicago Manual of Style (16th Edition):
Cook, William McKinley. “Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.” 2014. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/158626.
MLA Handbook (7th Edition):
Cook, William McKinley. “Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D.” 2014. Web. 05 Mar 2021.
Vancouver:
Cook WM. Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. [Internet] [Masters thesis]. Texas A&M University; 2014. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/158626.
Council of Science Editors:
Cook WM. Multi-Dimensional Nodalization of a Pressurized Water Reactor Core Using RELAP5-3D. [Masters Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/158626

Texas A&M University
10.
Kyriakopoulos, Vasileios.
Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.
Degree: MS, Nuclear Engineering, 2016, Texas A&M University
URL: http://hdl.handle.net/1969.1/159105
► This thesis examines five chemical solutions that are considered to be representative of the solution created in the containment sump during a postulated LOCA (loss…
(more)
▼ This thesis examines five chemical solutions that are considered to be representative of the solution created in the containment sump during a postulated LOCA (loss of coolant accident) at a Pressurized Water Reactor (PWR) power plant. In order to compare these solutions this study examines the head-loss response they produce through a prototypical sump strainer covered with a conventional fibrous debris bed.
Eleven experiments were conducted at TAMU’s vertical loop facility and four tests were selected for the purposes of this study. The test procedure started with a conventional debris bed being formulated on the sump strainer. Then followed the injection of the chemical solutions. The pressure drop through the debris bed and the approach velocity were monitored and recorded, among other parameters of interest.
The analysis of the results provided important insight on the relationship between the characteristics of the solutions and the response of the conventional debris bed. The results of this analysis provide valuable guidelines on the choice of chemical solutions to be used in further experimental research.
Advisors/Committee Members: Hassan, Yassin A (advisor), Vaghetto, Rodolfo (committee member), King, Maria (committee member).
Subjects/Keywords: GSI-191; strainer; PWR; nuclear
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APA ·
Chicago ·
MLA ·
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CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Kyriakopoulos, V. (2016). Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/159105
Chicago Manual of Style (16th Edition):
Kyriakopoulos, Vasileios. “Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.” 2016. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/159105.
MLA Handbook (7th Edition):
Kyriakopoulos, Vasileios. “Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.” 2016. Web. 05 Mar 2021.
Vancouver:
Kyriakopoulos V. Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/159105.
Council of Science Editors:
Kyriakopoulos V. Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/159105

Texas A&M University
11.
Chu, Hung-Chieh.
Application of the Fictitious Domain Method to Flow Problems with Complex Geometries.
Degree: PhD, Mechanical Engineering, 2017, Texas A&M University
URL: http://hdl.handle.net/1969.1/161671
► In this study, in order to address the immersed boundary condition, which was the critical issue regarding the fictitious domain method, two new strategies for…
(more)
▼ In this study, in order to address the immersed boundary condition, which was the critical issue regarding the fictitious domain method, two new strategies for addressing the numerical integral related to the immersed boundary condition were introduced. In the first strategy, the constraint was set to live everywhere, but only equaled the desired values in the area outside the needed domain. As to the second strategy, a boundary region was conceptually generated to replace the immersed boundary. An additional function, k(x), was added as a weight function to validate this replacement. Both of these strategies transfer boundary integrals to domain integrals that all computations can be finished by using the mesh generated for the fictitious domain. In addition, in order to deal with large scale problems, a modified iterative algorithm was proposed.
Three different types of problems were studied to evaluate the capability of these two strategies. It is shown that both of these two strategies are capable of addressing problems with only one variable. However, the study of the Stokes problem indicates the second strategy is a superior choice to deal with problems with multiple variables. Finally, from the Navier-Stokes flow problem, it is concluded that the second strategy can solve large scale flow problems with complex geometries.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Bangerth, Wolfgang (advisor), Muliana, Anastasia H. (committee member), Goenezen, Sevan (committee member).
Subjects/Keywords: Fictitious domain method; FEM
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APA ·
Chicago ·
MLA ·
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Export
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APA (6th Edition):
Chu, H. (2017). Application of the Fictitious Domain Method to Flow Problems with Complex Geometries. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/161671
Chicago Manual of Style (16th Edition):
Chu, Hung-Chieh. “Application of the Fictitious Domain Method to Flow Problems with Complex Geometries.” 2017. Doctoral Dissertation, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/161671.
MLA Handbook (7th Edition):
Chu, Hung-Chieh. “Application of the Fictitious Domain Method to Flow Problems with Complex Geometries.” 2017. Web. 05 Mar 2021.
Vancouver:
Chu H. Application of the Fictitious Domain Method to Flow Problems with Complex Geometries. [Internet] [Doctoral dissertation]. Texas A&M University; 2017. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/161671.
Council of Science Editors:
Chu H. Application of the Fictitious Domain Method to Flow Problems with Complex Geometries. [Doctoral Dissertation]. Texas A&M University; 2017. Available from: http://hdl.handle.net/1969.1/161671

Texas A&M University
12.
Delgado, Marilyn Irene.
High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry.
Degree: MS, Nuclear Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/173537
► The helical coil steam generator is a type of tube and shell heat exchanger that is proposed for many small modular and Gen IV reactor…
(more)
▼ The helical coil steam generator is a type of tube and shell heat exchanger that is proposed for many small modular and Gen IV reactor designs. It is favored due to the higher heat transfer it provides compared to traditional U-tube steam generators, compact design and thermal stress flexibility. The arrangement of tubes, where the secondary two-phase fluid flows, determines the shell side, pressurized single phase flow. This study focuses on the fluid structures that form in the shell side flow when adjacent helical tube bundles coil in opposite directions. Two helical coil steam generator designs were created and studied using a high-resolution flow visualization technique, refractive index matching particle image velocimetry (PIV). Experiments focused on multiple planes across each test section for different lateral pitch tube arrangements at Re ~ 8,500. Two-dimensional image sequences captured with a high speed camera were processed to determine average velocity flow fields for x- and y-direction velocity components. Two main regions of flow develop between tube bundle arrangements, center streamline flow and recirculation regions below the tubes. Previous studies have shown these recirculation regions are responsible for the increase in heat transfer this geometry offers. Nevertheless, vortices that form in these regions have the potential to grow and enter the streamline, a phenomenon called vortex shedding. The frequency of this shedding behavior is currently correlated to lateral and transverse pitches between bundles. A comparative study showed that while the center streamline development remained consistent between helical coil steam generator models, the recirculation regions varied in strength and relative size. Areas with a larger lateral pitch, expected to have large recirculation development between the rods, did not have the highest velocity magnitude. These average velocity fields suggest that relative location along the coiling bundle also contributes to the vortex shedding behavior of the recirculation regions below the tubes. Future work aims to study the transient behavior of the flow to have an in-depth analysis of the relationship between lateral pitch, transverse pitch, radial location around the helical coil tube bundle and recirculation region development.
Advisors/Committee Members: Hassan, Yassin A (advisor), Vaghetto, Rodolfo (committee member), King, Maria (committee member).
Subjects/Keywords: Helical Coil Steam Generator; PIV; flow visualization
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Delgado, M. I. (2018). High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173537
Chicago Manual of Style (16th Edition):
Delgado, Marilyn Irene. “High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry.” 2018. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/173537.
MLA Handbook (7th Edition):
Delgado, Marilyn Irene. “High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry.” 2018. Web. 05 Mar 2021.
Vancouver:
Delgado MI. High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/173537.
Council of Science Editors:
Delgado MI. High Resolution Measurements of Shell-Side Velocity Fields in Helical Coil Steam Generators Using Particle Image Velocimetry. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173537

Texas A&M University
13.
Alwafi, Anas Mohammed.
Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident.
Degree: MS, Nuclear Engineering, 2015, Texas A&M University
URL: http://hdl.handle.net/1969.1/187463
► Very High Temperature Reactors (VHTRs) are the future of nuclear reactors. A 1/16th scaled upper plenum of a VHTR was designed and assembled at Texas…
(more)
▼ Very High Temperature Reactors (VHTRs) are the future of nuclear reactors. A 1/16th scaled upper plenum of a VHTR was designed and assembled at
Texas A&
M University (TAMU) in order to study the behavior of flow in the upper plenum of a VHTR. Flow was investigated under one major accident scenario, the Depressurized Conduction Cooldown (DCC); this occurs due to loss of force when operation is interrupted by loss of power. In this case, the fluid will have a natural convection, forcing it to flow to the upper plenum. Particle Tracking Velocimetry (PTV) was used to illustrate flow, using water as the working fluid. A PTV code was used to track the particles, and this was then averaged over all vectors after filtering out those that failed. All flow velocity compounds, such as the velocity magnitude, y-velocity, x-velocity, standard deviation, and flow streamlines were visualized. A sensitivity analysis was performed in order to confirm that the number of frames used was sufficient to reach a steady state. In addition, repeatability analysis was applied to the output data. Turbulent intensity, Reynolds stress, and error occurring with these tests were all estimated. Finally, experimental data was validated using benchmark data.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H. (committee member), King, Maria D. (committee member).
Subjects/Keywords: PTV; VHTR; DCC; LOCA
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Alwafi, A. M. (2015). Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/187463
Chicago Manual of Style (16th Edition):
Alwafi, Anas Mohammed. “Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident.” 2015. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/187463.
MLA Handbook (7th Edition):
Alwafi, Anas Mohammed. “Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident.” 2015. Web. 05 Mar 2021.
Vancouver:
Alwafi AM. Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/187463.
Council of Science Editors:
Alwafi AM. Investigation of the Flow of the Upper Plenum of a Scaled Very High Temperature Reactor during a Depressurized Cooldown Conduction Accident. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/187463

Texas A&M University
14.
Larsen, Benjamin A.
Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model.
Degree: MS, Nuclear Engineering, 2014, Texas A&M University
URL: http://hdl.handle.net/1969.1/152740
► The current knowledge of flow parameters for terrestrial two-phase flow was developed through experiments that collected hundreds to thousands of data points. However, the cost…
(more)
▼ The current knowledge of flow parameters for terrestrial two-phase flow was
developed through experiments that collected hundreds to thousands of data points.
However, the cost associated with microgravity testing make collecting such amounts of
microgravity two-phase flow data difficult. Multiple researchers have postulated the
microgravity drift flux model parameters to predict void fraction, however, these
methods were initially developed with no consideration given to a microgravity
environment. The purpose of this thesis was to develop a process by which results from
multiple microgravity experiments can be compared on a similar medium and used to
develop a larger viable data set than what was previously available and to reliably
calculate a value for the void fraction from the available data.
Development of multiphase systems for microgravity requires accurate
prediction methods. Utilizing data from multiple microgravity two-phase flow
experiments, a statistically consistent slug flow database has been created. The data from
13 different microgravity two-phase flow experiments was vetted using a combination of
parametric and non-parametric statistical tests to develop a valid model for the drift flux
parameters that meet the axioms of a linear model. The result was a statistically
consistent microgravity slug flow data base consisting of 220 data points from 8
different experiments and the associated values for the concentration parameter, Co, and
drift velocity, u_(gj). A key component for this model was redefining the assumptions in
the drift flux model to accurately represent microgravity conditions in calculating the
drift flux parameters. The resultant drift flux parameters are a distribution parameter, Co
= 1.336 ± 0.013 and a drift velocity, u_(gj) = -0.126 ± 0.020.
Advisors/Committee Members: Vierow, Karen (advisor), Kurwitz, Richard (committee member), Hassan, Yassin A (committee member).
Subjects/Keywords: Drift Flux; Two-Phase Flow; Microgravity; Slug Flow
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
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Manager
APA (6th Edition):
Larsen, B. A. (2014). Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/152740
Chicago Manual of Style (16th Edition):
Larsen, Benjamin A. “Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model.” 2014. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/152740.
MLA Handbook (7th Edition):
Larsen, Benjamin A. “Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model.” 2014. Web. 05 Mar 2021.
Vancouver:
Larsen BA. Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model. [Internet] [Masters thesis]. Texas A&M University; 2014. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/152740.
Council of Science Editors:
Larsen BA. Statistical Analysis of Microgravity Two-Phase Slug Flow via the Drift Flux Model. [Masters Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/152740

Texas A&M University
15.
Abdulsattar, Suhaeb S.
Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers.
Degree: MS, Nuclear Engineering, 2014, Texas A&M University
URL: http://hdl.handle.net/1969.1/152832
► Safety related issues in Nuclear Power Plants (NPPs) have always been of concern, especially those issues that are related to Light Water Reactors (LWRs) and…
(more)
▼ Safety related issues in Nuclear Power Plants (NPPs) have always been of
concern, especially those issues that are related to Light Water Reactors (LWRs) and
their Design Basis Accidents (DBA). One of the ongoing issues that has been
extensively studied is the Generic Safety Issue GSI-191, which is dedicated to study and
resolve the issues that arise after a Loss-Of-Coolant-Accident (LOCA). Fibrous debris
produced during the blow-down phase of Loss-of-Coolant Accidents is transported into
the sump and becomes an important cause of head loss through the sump strainer,
affecting the Emergency Core Cooling System (ECCS) performance. This study was
dedicated to measure the pressure drop across randomly accumulated debris bed on the
sump strainer along with measuring the debris bed thickness. Two different types of
strainers were installed vertically, one at a time, in a horizontal flow loop and the debris
bed thickness was measured during the bed build up process and after reaching steady
state. Fifteen tests were conducted to determine the head loss difference between the two
strainers and to study the characteristics of the debris bed accumulated on each strainer.
The results from this experimental study were compared based on the approaching
velocity, debris bed thickness, and strainer type. A realistic permeability model for the
NUKON fiber glass insulation material was suggested, to be utilized in related
applications, the suggested head loss model was compared to other head loss models
developed in previous studies. The permeability model was developed from
experimental data acquired from approaching velocities in the viscous region. There was
no significant head loss difference between the two strainers for the minimum and intermediate range. Based on the experimental data, the head loss difference between the two strainers for the maximum range was about four times higher than the calculated head loss. The flow rate measurement uncertainty was main reason for the difference in the maximum range. There is a probability that the debris bypass could be different between the two strainers, thus, a debris bypass study is required to further investigate this difference.
Advisors/Committee Members: Hassan, Yassin A (advisor), Marlow, William H (committee member), Ugaz, Victor M (committee member).
Subjects/Keywords: Fibrous debris; Head loss; Sump strainer; Perforated Strainer; Porous media; Permeability; Kozeny constant; Loss-Of-Coolant-Accident (LOCA); NUKON fiber glass insulation; Generic Safety Issue GSI-191
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❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Abdulsattar, S. S. (2014). Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/152832
Chicago Manual of Style (16th Edition):
Abdulsattar, Suhaeb S. “Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers.” 2014. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/152832.
MLA Handbook (7th Edition):
Abdulsattar, Suhaeb S. “Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers.” 2014. Web. 05 Mar 2021.
Vancouver:
Abdulsattar SS. Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers. [Internet] [Masters thesis]. Texas A&M University; 2014. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/152832.
Council of Science Editors:
Abdulsattar SS. Head Loss Through Fibrous Debris Bed with Different Types of Perforated Strainers. [Masters Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/152832

Texas A&M University
16.
Hsu, Chia-Hsiang.
Enhancement of Pool Boiling Heat Transfer in Confined Space.
Degree: MS, Mechanical Engineering, 2014, Texas A&M University
URL: http://hdl.handle.net/1969.1/152843
► Pool boiling is an effective method used in many technical applications for a long time. Its highly efficient heat transfer performance results from not only…
(more)
▼ Pool boiling is an effective method used in many technical applications for a long
time. Its highly efficient heat transfer performance results from not only the convection
effect but also the phase change process in pool boiling. Pool boiling enhancement has
been studied in the past decade. However, the mechanisms of pool boiling has not yet
been fully understood because of the many parameters that affect its behavior including
the latent heat of vaporization, nucleation density, bubble and fluid motion, interaction at
the interface, and the physical properties of surface. Among the current studies, bubble
departure rate is viewed as one of the dominant factors that affect heat transfer.
This research considers the effect of bubble confinement on pool boiling. In the
study, confinement was achieved by placing a flat plate over heated surface. The flat
plate has a hole in the middle, and there is a gap between the flat plate and the heater.
The diameters of hole are 2 mm, 3 mm, and 4 mm; the gap distances are 2.3 mm, 3.6 mm,
and 5 mm. The heater consists of an indium-tin-oxide layer deposited on a silicon wafer. An IR
camera and high speed cameras are used to acquire the surface temperature distribution
and bubble image. By controlling the plate hole size and the gap distance, the effect of
confinement on heat transfer performance can be evaluated. Moreover, heat transfer
performance of pool boiling with three-2mm-holes plate was investigated and compared
with that of single-2mm-hole plate with the smallest gap size.
At the lower heat flux values, heat transfer enhancement in confined space was
experimentally observed. Surface temperature can be reduced by 4 °C at most. Results
indicate that higher bubble departure rate and coalescence effect might be the dominant factor for improving heat transfer performance in a confined space caused by induced shear flow.
Advisors/Committee Members: Alvarado, Jorge L. (advisor), Hassan, Yassin A. (committee member), Banerjee, Debjyoti (committee member).
Subjects/Keywords: Pool boiling; Confined space
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Hsu, C. (2014). Enhancement of Pool Boiling Heat Transfer in Confined Space. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/152843
Chicago Manual of Style (16th Edition):
Hsu, Chia-Hsiang. “Enhancement of Pool Boiling Heat Transfer in Confined Space.” 2014. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/152843.
MLA Handbook (7th Edition):
Hsu, Chia-Hsiang. “Enhancement of Pool Boiling Heat Transfer in Confined Space.” 2014. Web. 05 Mar 2021.
Vancouver:
Hsu C. Enhancement of Pool Boiling Heat Transfer in Confined Space. [Internet] [Masters thesis]. Texas A&M University; 2014. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/152843.
Council of Science Editors:
Hsu C. Enhancement of Pool Boiling Heat Transfer in Confined Space. [Masters Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/152843

Texas A&M University
17.
Chance, Christopher.
Partial Core Blockage Simulation Using COBRA-TF.
Degree: MS, Nuclear Engineering, 2014, Texas A&M University
URL: http://hdl.handle.net/1969.1/153903
► COBRA—TF (CTF) was used to simulate the cooling capabilities for two reactor types that undergo different blockage scenarios. One case considered is a pool-type TRIGA…
(more)
▼ COBRA—TF (CTF) was used to simulate the cooling capabilities for two reactor types that undergo different blockage scenarios. One case considered is a pool-type TRIGA reactor in which instrumentation tubes were inserted into existing coolant channels. The inclusion of the instrumentation tubes reduces the available coolant flow area, requiring an investigation of fuel coolability. The second case considered a pressurized water reactor (PWR) that has experienced a loss of coolant accident. Debris not stopped by the sump strainer can be deposited at the inlet of the core, creating blockage at the inlet of select assemblies. The blockage at the inlets could create a lack of cooling capability for the blocked assemblies and could result in fuel failure. CTF has not been widely used for testing these scenarios and the results should be compared alongside other simulations performed in STAR-CCM+ and RELAP5-3D.
. For the TRIGA reactor simulations, limitations of CTF were discovered such as a lack of natural convection correlations and setbacks with transient simulations. Therefore, steady-state simulations were created based on input data from the Safety Analysis Report for the reactor and data obtained by STAR-CCM+ models of the core. Single pin analyses were conducted on 3 different fuel rods in order to determine if the fuel rods were at risk of overheating from the proposed modifications with the instrumentation tubes. Larger simulations that modeled two different 4x4 arrays of fuel rods within the TRIGA core were used to determine how well the coolant traversed through these areas with the instrumentation tubes inserted. The results for all simulations were compared to STAR-COM+ results from similar models and it was determined that the insertion of the instrumentation tubes in the TRIGA reactor would not be a concern for the safety of the reactor under normal operating conditions.
The PWR simulations revealed more limitations of CTF and did not prove fruitful in providing reliable results. The original goal was to employ CTF to model a PWR core in full detail in order to compare the results to the RELAP5-3D model that used a lumped approach. However, we encountered difficulties with CTF, mostly due to issues with transient simulations and parallel processing. Significant improvements were made to CTF over the course of this research and have resulted in a more robust and bug-free version of the code. However, CTF is still being developed and has some remaining hurdles to overcome before it can be used to reliably model the simulations that were planned. This research still continues today and CTF is being used and improved upon to become a more versatile sub-channel analysis code.
Advisors/Committee Members: Ragusa, Jean C (advisor), Hassan, Yassin A (advisor), Chen, Hamn-Ching (committee member).
Subjects/Keywords: sub-channel analysis; thermal hydraulics; COBRA-TF
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APA (6th Edition):
Chance, C. (2014). Partial Core Blockage Simulation Using COBRA-TF. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/153903
Chicago Manual of Style (16th Edition):
Chance, Christopher. “Partial Core Blockage Simulation Using COBRA-TF.” 2014. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/153903.
MLA Handbook (7th Edition):
Chance, Christopher. “Partial Core Blockage Simulation Using COBRA-TF.” 2014. Web. 05 Mar 2021.
Vancouver:
Chance C. Partial Core Blockage Simulation Using COBRA-TF. [Internet] [Masters thesis]. Texas A&M University; 2014. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/153903.
Council of Science Editors:
Chance C. Partial Core Blockage Simulation Using COBRA-TF. [Masters Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/153903

Texas A&M University
18.
Sarikurt, Fatih Sinan.
CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel.
Degree: MS, Nuclear Engineering, 2015, Texas A&M University
URL: http://hdl.handle.net/1969.1/155266
► One of the most important parameters in the analysis of containment safety of the light water reactors during a loss of coolant accident (LOCA) is…
(more)
▼ One of the most important parameters in the analysis of containment safety of the light water reactors during a loss of coolant accident (LOCA) is the prediction of the hydrogen concentration. To ensure proper design of the containment to mitigate the fire/explosive risk created by the flammable hydrogen gas, this concentration build up must be analyzed. Lumped parameter (LP) codes are the main tools used in containment thermal-hydraulic analysis. However, they are limited when it comes to scenarios which require higher fidelity analysis of local phenomena. While the use of computational fluid dynamics (CFD) allows for higher fidelity analyses, CFD requires a comprehensive validation study due to turbulence and condensation modeling.
During a LOCA accident, the leaked hydrogen from the primary circuit can form a stable stratified layer at the top of the containment building. The formation and erosion of a stratified layer is a challenging numerical problem due to the interaction mechanism of the jet flow with the stratified layer. The OECD-NEA conducted an experiment at the Paul Scherrer Institute (PSI) as a part of the third International Benchmark Study (IBE-3) to investigate the erosion of the stratified layer by a vertical air-helium jet from the bottom of the large vessel. During the experiment, CFD grade experimental data was generated that could be used for comparative studies.
In the present study, the experiment is simulated by using the STAR-CCM+ CFD code with various turbulence models including Reynolds-Averaged Navier-Stokes (RANS) models and Large Eddy Simulation (LES). The Realizable k-ε and k-ω SST showed good agreement with the experimental when predicting the erosion of the stratified layer and global mixing of the gas components. The LES model also showed good agreement for velocity and faster erosion with experimental data, while the cost of the LES simulation was much higher than RANS simulations. The current validation study contributes to the sensitivity analysis of the turbulence models for erosion behavior in the stratified layer. In addition to that, the results of this study will provide a foundation to discuss the feasibility of the CFD code usage in containment level thermal hydraulic analysis.
Advisors/Committee Members: Hassan, Yassin A (advisor), Marlow, William H (committee member), King, Maria (committee member).
Subjects/Keywords: buoyancy jet; stratified layer; containment safety; cfd; turbulence
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APA (6th Edition):
Sarikurt, F. S. (2015). CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155266
Chicago Manual of Style (16th Edition):
Sarikurt, Fatih Sinan. “CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel.” 2015. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/155266.
MLA Handbook (7th Edition):
Sarikurt, Fatih Sinan. “CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel.” 2015. Web. 05 Mar 2021.
Vancouver:
Sarikurt FS. CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/155266.
Council of Science Editors:
Sarikurt FS. CFD Simulations of Erosion of a Stratified Layer by a Buoyant Jet in a Large Vessel. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155266

Texas A&M University
19.
Khan, Abdul.
Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm.
Degree: MS, Nuclear Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11730
► In this study, the phenomenon of two-phase flow was investigated in a square channel. The experiment was performed with stagnant liquid conditions. The gas and…
(more)
▼ In this study, the phenomenon of two-phase flow was investigated in a square channel. The experiment was performed with stagnant liquid conditions. The gas and liquid dynamics of the bubbly flow were observed in two regions far from the inlet. Air was inserted through a porous media at three superficial gas velocities: 4.6 mm/s, 2.5 mm/s, and 1.4 mm/s.
Two techniques were applied in the experiment to measure the bubbly flow: an optical probe and an in-house developed tracking algorithm. Measurements of the bubble interface velocity, void fraction, bubble frequency, time of flight, and Sauter mean diameter were obtained by using the optical probe. The duration of the probe measurements for all three flow rates and both regions lasted approximately 33 hours. The tracking algorithm was used to analyze the experimental data for two visual methods: shadowgraphy and Particle Tracking Velocimetry (PTV). Shadowgraphy provided gas-phase measurements of the bubble centroid velocity and its fluctuations, void fraction, bubble size, and Reynolds stresses. Five data sets were acquired for each flow rate, resulting in a total of 327,540 shadowgraphy images. Liquid parameters such as the velocity, fluctuations in the velocity, and the Reynolds stresses were provided by PTV. Only one data set containing 10,918 images was obtained from liquid measurements for each flow rate. One data set was sufficient to provide reliable statistics since tracking two consecutive images lead to approximately 15,000 velocity vectors. The data obtained from this study was an effort to assist in the verification, validation, and improvement of two-phase flow simulations.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H. (committee member), Annamalai, Kalyan (committee member).
Subjects/Keywords: Optical Probe; Shadowgraphy; PTV; Tracking Algorithm; Bubbly Flow; Two Phase Flow
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Khan, A. (2012). Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11730
Chicago Manual of Style (16th Edition):
Khan, Abdul. “Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11730.
MLA Handbook (7th Edition):
Khan, Abdul. “Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm.” 2012. Web. 05 Mar 2021.
Vancouver:
Khan A. Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11730.
Council of Science Editors:
Khan A. Bubbly Flow Experiment in Channel Using an Optical Probe and Tracking Algorithm. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11730

Texas A&M University
20.
Wang, Huhu 1985-.
CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor.
Degree: MS, Nuclear Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/148310
► Very High Temperature Rector (VHTR) had been designated as one of those promising reactors for the Next Generation (IV) Nuclear Plant (NGNP). For a prismatic…
(more)
▼ Very High Temperature Rector (VHTR) had been designated as one of those promising reactors for the Next Generation (IV) Nuclear Plant (NGNP). For a prismatic core VHTR, one of the most crucial design considerations is the bypass flow and crossflow effect. The bypass flow occurs when the coolant flow into gaps between fuel blocks. These gaps are formed as a result of carbon expansion and shrinkage induced by radiations and manufacturing and installation errors. Hot spots may appear in the core if the large portion of the coolant flows into bypass gaps instead of coolant channels in which the cooling efficiency is much higher.
A preliminary three dimensional steady-state CFD analysis was performed with commercial code STARCCM+ 6.04 to investigate the bypass flow and crossflow phenomenon in the prismatic VHTR core. The k-ε turbulence model was selected because of its robustness and low computational cost with respect to a decent accuracy for varied flow patterns. The wall treatment used in the present work is two-layer all y+ wall treatment to blend the wall laws to estimate the shear stress. Uniform mass flow rate was chose as the inlet condition and the outlet condition was zero gauge pressure outlet.
Grid independence study was performed and the results indicated that the discrepancy of the solution due to the mesh density was within 2% of the bypass flow fraction. The computational results showed that the bypass flow fraction was around 12%. Furthermore, the presence of the crossflow gap resulted in a up to 28% reduction of the coolant in the bypass flow gap while mass flow rate of coolant in coolant channels increased by around 5%. The pressure drop at the inlet due to the sudden contraction in area could be around 1kpa while the value was about 180 Pa around the crossflow gap region. The error analysis was also performed to evaluate the accumulated errors from the process of discretization and iteration. It was found that the total error was around 4% and the variation for the bypass flow fraction was within 1%.
Advisors/Committee Members: Hassan, Yassin A (advisor), Marlow, William H (committee member), Chen, Hamn-Ching (committee member).
Subjects/Keywords: Crossflow; Bypass flow; Prismatic VHTR
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Wang, H. 1. (2012). CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148310
Chicago Manual of Style (16th Edition):
Wang, Huhu 1985-. “CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/148310.
MLA Handbook (7th Edition):
Wang, Huhu 1985-. “CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor.” 2012. Web. 05 Mar 2021.
Vancouver:
Wang H1. CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/148310.
Council of Science Editors:
Wang H1. CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148310

Texas A&M University
21.
Rodriguez, Oscar.
RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes.
Degree: MS, Mechanical Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/148410
► RELAP5-3D has been coupled with both DAKOTA and STAR-CCM+ in order to expand the capability of the thermal-hydraulic code and facilitate complex studies of desired…
(more)
▼ RELAP5-3D has been coupled with both DAKOTA and STAR-CCM+ in order to expand the capability of the thermal-hydraulic code and facilitate complex studies of desired systems. In the first study, RELAP5-3D was coupled with DAKOTA to perform a sensitivity study of the South
Texas Project (STP) power plant during steady-state and transient scenarios. The coupled software was validated by analyzing the simulation results with respect of the physical expectations and behavior of the power plant, and thermal-hydraulic parameters which caused greatest sensitivity where identified: inlet core temperature and reactor thermal power. These variables, along with break size and discharge coefficients, were used for further investigation of the sensitivity of the RELAP5-3D LOCA transient simulation under three difference cases: two inch break, six inch break, and guillotine break. Reactor thermal power, core inlet temperature, and break size were identified as producing the greatest sensitivity; therefore, future research would include uncertainty quantification for these parameters. In the second study, a small scale experimental facility, designed to study the thermal hydraulic phenomena of the Reactor Cavity Cooling System (RCCS) for a Very High Temperature Reactor (VHTR), was used as a model to test the capabilities of coupling Star-CCM+ and RELAP5-3D. This chapter discusses the capabilities and limitations of the STAR-CCM+/RELAP5-3D coupling, and a simulation, on the RCCS facility, was performed using STAR-CCM+ to study the flow patterns where expected complex flow phenomena occur and RELAP5-3D for the complete system. The code showed inability to perform flow coupling simulations and it is unable, at this time, to handle closed loop systems. The thermal coupling simulation was successful and showed congruent qualitative results to physical expectations. The locations of large fluid vortices were located specifically in the pipes closest to the inlet of the bottom manifold. In conclusion, simulations using coupled codes were presented which greatly improved the capabilities of RELAP5-3D stand-alone and computational time required to perform complex thermal-hydraulic studies. These improvements show greatly benefit for industrial applications in order to perform large scale thermal-hydraulic systems studies with greater accuracy while minimizing simulation time.
Advisors/Committee Members: Hassan, Yassin A (advisor), Marlow, William H (advisor), Jacobs, Timothy J (committee member).
Subjects/Keywords: Nuclear CFD; thermal hydraulics
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Rodriguez, O. (2012). RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148410
Chicago Manual of Style (16th Edition):
Rodriguez, Oscar. “RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/148410.
MLA Handbook (7th Edition):
Rodriguez, Oscar. “RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes.” 2012. Web. 05 Mar 2021.
Vancouver:
Rodriguez O. RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/148410.
Council of Science Editors:
Rodriguez O. RELAP5-3D Thermal Hydraulics Computer Program Analysis Coupled with DAKOTA and STAR-CCM+ Codes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148410

Texas A&M University
22.
Lakshmipathy, Sathish Kumar.
VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D.
Degree: MS, Nuclear Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11188
► Improving core performance by reshuffling/reloading the fuel blocks within the core is one of the in-core fuel management methods with two major benefits: a possibility…
(more)
▼ Improving core performance by reshuffling/reloading the fuel blocks within the core is one of the in-core fuel management methods with two major benefits: a possibility to improve core life and increase core safety. VHTR is a hexagonal annular core reactor with reflectors in the center and outside the fuel rings (3-rings). With the block type fuel assemblies, there is an opportunity for muti-dimensional fuel bocks movement within the core during scheduled reactor refueling operations.
As the core is symmetric, by optimizing the shuffle operation of 1/6th of the core, the same process can be repeated through the remaining 5/6th of the core. VHTR has 170 fuel blocks in the core of which 50 are control rod blocks and are not movable to regular fuel block locations. The reshuffling problem now is to find the best combination of 120 fuel blocks that has a minimized power peaking and/or increased core life under safety constraints among the 120! combinations.
For evaluating each LP during the shuffling, a fitness function that is developed from the parameters affecting the power peaking and core life is required. Calculating the power peaking at each step using Monte Carlo simulations on a whole core exact geometry model is a time consuming process and not feasible. A parameter is developed from the definitions of reactivity and power peaking factor called the localized reactivity potential that can be estimated for every block movement based on the reaction rates and atom densities of the initial core burnup at the time of shuffling.
The algorithm (ReloPSO) is based on Particle Swarm Optimization algorithm the search process by improving towards the optimum from a set of random LPs based on the fitness function developed with the reactivity potential parameter. The algorithm works as expected and the output obtained has a flatter reactivity profile than the input. The core criticality is found to increase when shuffled closer to end of life. Detailed analysis on the burn runs after shuffling at different time of core operation is required to correlate the estimated and actual values of the reactivity parameter and to optimize the time of shuffle.
Advisors/Committee Members: Tsvetkov, Pavel V. (advisor), Hassan, Yassin A. (committee member), Curry, Guy L. (committee member).
Subjects/Keywords: Particle Swarm Optimization; Core shuffling optimization
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Lakshmipathy, S. K. (2012). VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11188
Chicago Manual of Style (16th Edition):
Lakshmipathy, Sathish Kumar. “VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11188.
MLA Handbook (7th Edition):
Lakshmipathy, Sathish Kumar. “VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D.” 2012. Web. 05 Mar 2021.
Vancouver:
Lakshmipathy SK. VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11188.
Council of Science Editors:
Lakshmipathy SK. VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11188

Texas A&M University
23.
Vaghetto, Rodolfo.
Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion.
Degree: MS, Nuclear Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/ETD-TAMU-2011-05-9225
► An experimental activity was performed to observe and study the effects of graphite dispersion and deposition on thermal hydraulic phenomena in a Reactor Cavity Cooling…
(more)
▼ An experimental activity was performed to observe and study the effects of graphite dispersion and deposition on thermal hydraulic phenomena in a Reactor Cavity Cooling System (RCCS). The small scale RCCS experimental facility (16.5cm x 16.5cm x 30.4cm) used for this activity represents half of the reactor cavity with an electrically heated vessel. Water flowing through five vertical pipes removes the heat produced in the vessel and releases it in the environment by mixing with cold water in a large tank. PIV technique was used to study the velocity field of the air inside the cavity. A set of 52 thermocouples was installed in the facility to monitor the temperature profiles of the vessel and pipes walls and air. 10g of a fine graphite powder (particle size average 2 [mu]
m) were injected into the cavity through a spraying nozzle placed at the bottom of the vessel. Temperatures and air velocity field were recorded and compared with the measurements obtained before the graphite dispersion, showing a decrease of the temperature surfaces which was related to an increase in their emissivity. The results contribute to the understanding of the RCCS capability in case of an accident scenario.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H. (committee member), Ugaz, Victor M. (committee member).
Subjects/Keywords: Reactor Cavity Cooling System; Radiation Heat Transfer; Graphite Dispersion
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Vaghetto, R. (2012). Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2011-05-9225
Chicago Manual of Style (16th Edition):
Vaghetto, Rodolfo. “Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion.” 2012. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/ETD-TAMU-2011-05-9225.
MLA Handbook (7th Edition):
Vaghetto, Rodolfo. “Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion.” 2012. Web. 05 Mar 2021.
Vancouver:
Vaghetto R. Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-05-9225.
Council of Science Editors:
Vaghetto R. Experimental Study of the Thermal-Hydraulic Phenomena in the Reactor Cavity Cooling System and Analysis of the Effects of Graphite Dispersion. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-05-9225

Texas A&M University
24.
Capone, Luigi.
CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors.
Degree: PhD, Nuclear Engineering, 2012, Texas A&M University
URL: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11404
► The analysis of the turbulent flows in nuclear fuel bundles is a very interesting task to optimize the efficiency of modern nuclear power plants. The…
(more)
▼ The analysis of the turbulent flows in nuclear fuel bundles is a very interesting task to optimize the efficiency of modern nuclear power plants. The proposed study utilizes Computational Fluid Dynamics (CFD) to characterize the flow pattern generated in a fuel bundle with Spacer Grids (SG) and Mixing Vanes (MV). CFD calculations were performed using different turbulence models for steady state simulations. Large Eddy Simulations (LES) scheme was applied to time dependent cases. The simulations were compared with the experimental data measured at
Texas A&
M University fuel bundle experimental facility. Also, another objective is to develop some new coarse mesh approaches for modeling MV to include these structures in the prospective of quarter of core simulations; MV and SG are usually modeled with porous media, since the computational power required to solve the full geometry is still unacceptable. The new contribution of the study is the definition and implementation of a Momentum Sources Forcing approach that allows a detailed definition of MV and SG for coarse mesh calculations. The proposed method was investigated using different turbulence models and different numerical schemes. Also, LES calculations allowed the study of Fluid Structure Interaction (FSI), that generates vibration problems and failure of nuclear fuel pins. A spectral analysis of the forces acting on the fuel pins walls was developed. In conclusion, a comprehensive study of fuel bundle problem was proposed with benchmark of the computational techniques to the experimental data.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Annamalai, Kilyan (advisor), Ugaz, Victor (committee member), Marlow, William H. (committee member).
Subjects/Keywords: Spacer Grids; Mixing Vanes; Momentum Sources; Source Forcing Method, CFD
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
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APA (6th Edition):
Capone, L. (2012). CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11404
Chicago Manual of Style (16th Edition):
Capone, Luigi. “CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors.” 2012. Doctoral Dissertation, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11404.
MLA Handbook (7th Edition):
Capone, Luigi. “CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors.” 2012. Web. 05 Mar 2021.
Vancouver:
Capone L. CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors. [Internet] [Doctoral dissertation]. Texas A&M University; 2012. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11404.
Council of Science Editors:
Capone L. CFD Analysis of Nuclear Fuel Bundles and Spacer Grids for PWR Reactors. [Doctoral Dissertation]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11404

Texas A&M University
25.
Kappes, Matthew Jareb.
Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor.
Degree: MS, Nuclear Engineering, 2015, Texas A&M University
URL: http://hdl.handle.net/1969.1/155627
► During a LOCA in a LWR, a containment-sump strainer filters debris, generated from fibrous thermal insulation, from the water collected in the containment sump. The…
(more)
▼ During a LOCA in a LWR, a containment-sump strainer filters debris, generated from fibrous thermal insulation, from the water collected in the containment sump. The buildup of debris on the strainer and the bypass of debris through the strainer lead to upstream and downstream effects, respectively.
The objective of this research was to create a methodology for obtaining PSDs for this debris upstream and downstream of a sump strainer in multiple size ranges. Fibrous debris was injected into an experimental facility which simulated the conditions in a LWR containment sump. Samples were taken downstream of the strainer during the experiment. Using a NanoSight LM10 and two optical microscope systems, size measurements of particles were made.
The fractional number of particles between 55-188 nm increased from 0.591 to 0.734 upstream to downstream; the number of all other particle sizes decreased. This trend is consistent with Hutten’s [8] statements about the MPPS. For AMIS-1, from upstream to downstream, the fraction of particles smaller than 55 μ
m increased from 0.77 to 0.89; almost all of the larger particles sizes decreased in number. This demonstrates larger particles being more efficiently filtered. For AMIS-2, from upstream to downstream, the fraction of particles smaller than 340 μ
m increased from 0.536 to 0.668; all of the larger particle sizes decreased in number. This again demonstrates higher filtration efficiency for larger particles.
Different PDFs provided the best fit for the PSDs in each of the size ranges measured. For the nanometer range, the Johnson’s SB function provided the best fit. For the 10-500 μ
m range, the upstream and downstream results were fit best with the log-logistic and lognormal functions, respectively. For the 100-2500 μ
m size range, the Weibull distribution was found to fit best. Changes in the PDFs fit to the upstream and downstream PSDs were similar to what was found when comparing the upstream and downstream PSD histograms.
Size distributions for spherical (tin powder) and angular (SiC F600) particles were easily obtained using the Coulter Counter, however, it didn’t provide reliable results for fibrous debris.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H. (committee member), King, Maria D. (committee member).
Subjects/Keywords: LOCA; containment sump; strainer; debris bypass; fibrous debris; particle size distribution; fibrous porous media
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APA (6th Edition):
Kappes, M. J. (2015). Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155627
Chicago Manual of Style (16th Edition):
Kappes, Matthew Jareb. “Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor.” 2015. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/155627.
MLA Handbook (7th Edition):
Kappes, Matthew Jareb. “Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor.” 2015. Web. 05 Mar 2021.
Vancouver:
Kappes MJ. Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/155627.
Council of Science Editors:
Kappes MJ. Particle Size Distributions of Debris Upstream and Downstream of the Containment Sump Strainer in a Light Water Reactor. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155627

Texas A&M University
26.
Spear, Aubrey Alvin.
Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel.
Degree: MS, Mechanical Engineering, 2015, Texas A&M University
URL: http://hdl.handle.net/1969.1/174811
► Government regulations on emission standards and constantly fluctuating fuel availability and prices have led to the need of more readily usable and available models for…
(more)
▼ Government regulations on emission standards and constantly fluctuating fuel availability and prices have led to the need of more readily usable and available models for power generating combustors. A common, versatile, power generating combustor is the circulating fluidized bed (CFB) boiler. Waste tire is viewed as a potential fuel in a CFB boiler. Extensive literature review is used to create a model of a CFB boiler.
The model is programmed using Microsoft Excel software. The program consists of four major tabs being the ‘Input’, ‘Bed’, ‘Riser’, and ‘Output’ tabs. The ‘Input’ tab consists of appropriate and minimal input parameters to allow for enough variability while not over burdening the user with acquiring large amounts of data. The ‘Bed’ tab describes the instantaneous chemical reactions assumed to take place in the dense bed region of the combustor. The ‘Riser’ tab tracks the time dependent chemical kinetics through a predetermined number of time steps divided evenly throughout the lean riser region of the combustor. The ‘Output’ tab calculates the concentration at the exit of the combustor riser for ten different species important to both combustion and government regulations being CO, H2O, O2, N2, NH3, HCN, SO2, CO2, H2, and NO. With 5,000 chemical kinetics calculation rows, the computation time for varying an input is approximately ten seconds.
The model has been validated against an anonymous industrial CFB boiler firing lignite coal fuel resulting in emission concentrations being 22% different or less between the model predictions and the actual emissions when kinetics are slightly modified. The model was also validated against a Babcock and Wilcox pilot/laboratory scale bubbling fluidized bed (BFB) boiler firing subbituminous coal fuel resulting in emission concentrations being 10% different at most between the model predictions and the actual emissions without kinetics modification except for the O2 concentration being off by about 74% due to differences with CFB.
The anonymous CFB boiler had fuel switched to waste tire fuel, and 24 inputs were varied as part of a parametric analysis of the fuel to discover emission trends.
Advisors/Committee Members: Annamalai, Kalyan (advisor), Petersen, Eric L (committee member), Hassan, Yassin A (committee member).
Subjects/Keywords: Circulating; Fluidized; Bed; Boiler; Model; Emission; Fuel; Tire; Lignite; Coal; Combustion; Power; Generate; Combustor; Waste; Riser; Chemical; Kinetics; Reaction; Concentration; Parametric; Analysis; Computer; Excel; Pyrolysis; Devolatilization; Two-phase; Limestone; Calcination; Sulfation; Volatile; Ash; Residence; Burn; Particle; Terminal; Velocity; Diffusion; Nitrogen; Carbon; Hydrogen; Oxygen; Sulfur; Recirculation; Validation
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Spear, A. A. (2015). Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174811
Chicago Manual of Style (16th Edition):
Spear, Aubrey Alvin. “Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel.” 2015. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/174811.
MLA Handbook (7th Edition):
Spear, Aubrey Alvin. “Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel.” 2015. Web. 05 Mar 2021.
Vancouver:
Spear AA. Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/174811.
Council of Science Editors:
Spear AA. Circulating Fluidized Bed Boiler Model for Predicting Emission Levels of Tire Fuel using Base Case of Lignite Fuel. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/174811

Texas A&M University
27.
Budd, John Layne.
Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility.
Degree: MS, Mechanical Engineering, 2016, Texas A&M University
URL: http://hdl.handle.net/1969.1/156798
► To further efforts for studying the TAMU air-cooled Reactor Cavity Cooling System (RCCS) experimental test facility, Laser Doppler Velocimetry (LDV) experiments have been conducted to…
(more)
▼ To further efforts for studying the TAMU air-cooled Reactor Cavity Cooling System (RCCS) experimental test facility, Laser Doppler Velocimetry (LDV) experiments have been conducted to acquire data on the instantaneous streamwise and spanwise components of velocity at various locations inside the upper plenum. These experiments were performed under steady-state conditions, both heated and adiabatic, using four active risers. The apparatus used for data acquisition consisted primarily of a 2-D laser head mounted onto a 3-D traverse system. Olive oil particles with an average diameter of 0.745 µm were utilized for seeding the flow.
The data from these experiments has been necessary for characterizing the experimental facility by verifying the system’s repeatability and performance. In addition, LDV measurements have provided means of comparison for previously acquired PIV measurements. The compared parameters include the streamwise velocity component, as well as the streamwise and spanwise components of the turbulent intensity and the Reynolds stresses.
Based on these comparisons, several differences were found between the two techniques. First, the PIV turbulent statistics did not generally agree well with those of the LDV measurements. However, data points located at regions of higher elevation tended to have better agreement. These higher regions are characterized by velocity gradients significantly smaller than those found at lower elevations. This fact may aid in explaining the discrepancies between the techniques, since PIV is known to underperform on regions with high velocity gradients. In addition, it is suspected that the number of samples for PIV, 150 in total, were insufficient for obtaining reasonable statistics. This is in contrast to LDV, which had 1500 samples per data point. Second, the comparison between the techniques appear to agree better for the adiabatic case than the heated case. Since the heated case has additional turbulence fluctuations induced by thermal mixing, this may have hindered the PIV measurements. Third, the turbulence intensities were consistently overestimated by PIV. This led to the conclusion that the PIV data contained significantly more noise than LDV data.
Aside from comparisons between the two techniques, several experiments were conducted to test the repeatability and accuracy of the LDV measurements. It was found that the LDV measurements exhibited good accuracy and a high level of repeatability. Throughout these measurements, the standard deviation percentage was found to be no greater than 10%. More importantly, when averaging the values of all data points at each respective each elevation, the average value ranged between 2.2% and 3.5%.
Advisors/Committee Members: Hassan, Yassin A. (advisor), Marlow, William H. (advisor), King, Maria D. (advisor).
Subjects/Keywords: Reactor Cavity Cooling System; Passive Safety System; Laser Doppler Velocimetry; Particle Image Velocimetry
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APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Budd, J. L. (2016). Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156798
Chicago Manual of Style (16th Edition):
Budd, John Layne. “Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility.” 2016. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/156798.
MLA Handbook (7th Edition):
Budd, John Layne. “Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility.” 2016. Web. 05 Mar 2021.
Vancouver:
Budd JL. Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/156798.
Council of Science Editors:
Budd JL. Comparison between Particle Image Velocimetry and Laser Doppler Velocimetry Measurements inside the TAMU Reactor Cavity Cooling System Experimental Test Facility. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/156798

Texas A&M University
28.
Ullah, Izhar.
Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.
Degree: MS, Mechanical Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/173786
► This thesis is an experimental study to examine the effect of different hole shapes and coolant hole trajectory on film cooling effectiveness and discharge coefficient.…
(more)
▼ This thesis is an experimental study to examine the effect of different hole shapes and coolant hole trajectory on film cooling effectiveness and discharge coefficient. PSP technique was used to calculate the film cooling effectiveness and film cooling contours. Effect of hole geometry and trajectory was studied at different density ratios and different blowing ratios. Three different density ratios DR=1, DR=1.5 and DR = 2 were used and five blowing ratios from
M= 0.5 - 1.5 were used with an increment of 0.25. Diameter of the hole was taken as 4 mm. Three different exit geometries (Round to slot-, Round to annulus, Round to annulus2) were used with linear and projectile trajectories, thus making a total of six test plates.
Results obtained agreed with the general trend of shaped holes. It is interesting to observe that slot shaped exit hole is still a better option than annulus shaped holes. Slot shaped exit hole with projectile trajectory resulted in improved effectiveness with 30-40% increase in span wise effectiveness as compared to its linear slot shaped counterpart. This improved design at DR=2 which corresponds to the actual conditions of a real engine. However round to slot test plate with projectile trajectory has the lowest discharge coefficient implying more pressure requirement for the coolant at the same blowing ratio. Correlation was obtained for a single row different exit shaped holes.
Advisors/Committee Members: Han, Je-Chin (advisor), Hassan, Yassin A. (committee member), Pate, Michael (committee member).
Subjects/Keywords: Film cooling; Pressure sensitive paint (PSP)
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❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Ullah, I. (2018). Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173786
Chicago Manual of Style (16th Edition):
Ullah, Izhar. “Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.” 2018. Masters Thesis, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/173786.
MLA Handbook (7th Edition):
Ullah, Izhar. “Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique.” 2018. Web. 05 Mar 2021.
Vancouver:
Ullah I. Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/173786.
Council of Science Editors:
Ullah I. Flat Plate Film Cooling with Linear and Curved Round-to-Diffusion Shaped Slots Using PSP Measurement Technique. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173786

Texas A&M University
29.
Li, Han.
Computational Study of Interaction of Twin Rectangular Jets.
Degree: PhD, Mechanical Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/174415
► Turbulent jet interactions play a significant role in terms of momentum and heat transfer. Interactions of multiple turbulent jets occurs in next-generation nuclear reac- tors,…
(more)
▼ Turbulent jet interactions play a significant role in terms of momentum and heat
transfer. Interactions of multiple turbulent jets occurs in next-generation nuclear reac-
tors, where high-temperature flow mixing in the lower plenum and mixing fluctuations
in the coolant may influence power oscillations and flow-induced vibrations. Thus, the
estimation of mixing condition needs to be accurate. Recent benchmark experiments
using the particle image velocimetry (PIV) technique provided high-fidelity experi-
mental data that could be used in verification studies. Computational fluid dynamics
(CFD) simulations are extensively employed in the study of mixing phenomenon of
parallel jets. Therefore, the validation of various turbulence models is of great impor-
tance for ensuring that the numerical results are reliable and can serve as a guide for
future designs.
In this study, an open source CFD library, i.e., OpenFOAM, was utilized to con-
duct numerical simulations of twin jets. This work consists of two parts: one part
focuses on steady-state simulations and the other on transient simulations. In the first
part, the steady state Reynolds-averaged Navier-Stokes (RANS) models, such as the
realizable k - ϵ and the shear stress transport k - ɯ, were used for the steady-state val-
idation study. Steady-state simulations showed that with proper boundary conditions
at the inlets, the mean velocity data agreed well with the experimental data within
engineering accuracy (14%). In the second part, the partially averaged Navier - Stokes
(PANS) models were implemented in the code and were utilized to conduct transient
simulations. Fluctuating inlet boundary conditions from experiments were employed.
The results obtained from PANS and the unsteady RANS (URANS) models were com-
pared with experimental data. The PANS model showed a good agreement with the
experimental data in terms of the merging point (4.3%). In addition, the k - ϵ PANS
model was compared with the k - ϵ URANS model. A power spectrum density (PSD)
analysis was performed based on the velocity at four sample locations to compare the
resolved frequencies between the PANS and URANS models. It was observed that the
PANS model showed better capabilities of resolving higher turbulence flow frequencies
compared to the URANS based on the PSD analysis.
Another part of this study included the use of large eddy simulation numerical
methodology on a parallel jet system and the computational results were validated
against the benchmark PIV experiments. The results indicated a good agreement in
terms of the merging point and time-averaged velocity profile. Spectral analyses via
Welch’s power spectral density functions were used to analyze frequency information
in turbulent jets. The proper orthogonal decomposition (POD) analysis method was
applied using a snapshot method. The POD analysis showed vortex structures similar
to those in the benchmark PIV experiment.
Advisors/Committee Members: Anand, Nagamangala (advisor), Hassan, Yassin A (advisor), Chen, Hamn-Ching (committee member), King, Maria (committee member).
Subjects/Keywords: Turbulent mixing; Parallel jets; Computational fluid dynamics; OpenFOAM
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❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Li, H. (2018). Computational Study of Interaction of Twin Rectangular Jets. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174415
Chicago Manual of Style (16th Edition):
Li, Han. “Computational Study of Interaction of Twin Rectangular Jets.” 2018. Doctoral Dissertation, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/174415.
MLA Handbook (7th Edition):
Li, Han. “Computational Study of Interaction of Twin Rectangular Jets.” 2018. Web. 05 Mar 2021.
Vancouver:
Li H. Computational Study of Interaction of Twin Rectangular Jets. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/174415.
Council of Science Editors:
Li H. Computational Study of Interaction of Twin Rectangular Jets. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174415

Texas A&M University
30.
Kumar, Navin.
Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant.
Degree: PhD, Mechanical Engineering, 2018, Texas A&M University
URL: http://hdl.handle.net/1969.1/192060
► Conventional electric power production primarily relies on water as a coolant - to remove low grade heat from the steam exiting from the turbines in…
(more)
▼ Conventional electric power production primarily relies on water as a coolant - to remove low grade heat from the steam exiting from the turbines in thermal power-plants. It is anticipated that in the near future - these conventional techniques for water cooling of thermal power-plants will become unsustainable in various geographical regions that have scarcity of water resources. This is expected to arise from a combination of environmental concerns, increased water demand due to population growth, and the impact of climate change. Therefore, air-cooled platforms (dry cooling systems) are the obvious option for the replacement of water-cooled platforms. However, dry-cooling systems suffer from several performance limitations that compromise their reliability. Supplemental cooling systems can enhance the operational reliability and thermal performance of dry cooling systems. Hence, a latent heat thermal energy storage system (LHTESS) was developed and validated in this study as a proof of concept for a supplemental cooling system. The goal of this study to is to demonstrate the viability of LHTESS as a supplemental cooling platform with the aim of improving the energy efficiency and thermal performance ratings of air-cooled systems.
To improve the operational reliability of the LHTESS explored in this study, different phase change materials (PCMs) were explored (with and without additives). Both organic (e.g., paraffin) and inorganic (e.g., salt hydrates) materials were explored as candidate PCMs.
Material stability of the candidate PCM samples and additives were analyzed by subjecting them to thermocycling: consisting of repeated cycles of melting and freezing. Corrosion experiments were performed for evaluating the material compatibility of the chosen list of PCMs with candidate materials used in construction of LHTESS.
The incorporation of candidate PCMs in various heat exchanger configurations and validating their thermal performance was performed to meet the deliverables specified by the
sponsor of this research study, as part of the ARID program (Advanced Research in Dry-Cooling) of ARPA-E (Advanced Research Programs Agency – Energy). The different heat exchanger configurations explored in this study are: shell-and-tube heat exchanger (using Additive Manufacturing techniques, i.e., 3-D Printing), chevron-plate heat exchangers and a compact heat exchanger. Thermal conductivity enhancement techniques were explored by incorporating aluminum mesh as a metal foam in the compact heat exchanger.
Advisors/Committee Members: Banerjee, Debjyoti (advisor), Sai Lau (advisor), Hassan, Yassin A (committee member), Pharr, Matt (committee member).
Subjects/Keywords: Phase Change Material; Thermal Energy Storage; Salt Hydrates; Latent Heat
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❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Kumar, N. (2018). Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/192060
Chicago Manual of Style (16th Edition):
Kumar, Navin. “Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant.” 2018. Doctoral Dissertation, Texas A&M University. Accessed March 05, 2021.
http://hdl.handle.net/1969.1/192060.
MLA Handbook (7th Edition):
Kumar, Navin. “Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant.” 2018. Web. 05 Mar 2021.
Vancouver:
Kumar N. Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Mar 05].
Available from: http://hdl.handle.net/1969.1/192060.
Council of Science Editors:
Kumar N. Experimental Investigation of Latent Heat Energy Storage System (LHTESS) for Enhancing Performance of Dry-Cooling Powerplant. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/192060
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