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You searched for +publisher:"Texas A&M University" +contributor:("Tsvetkov, Pavel V."). Showing records 1 – 30 of 46 total matches.

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Texas A&M University

1. Scherr, Jonathan B. Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D.

Degree: MS, Nuclear Engineering, 2016, Texas A&M University

 The current US fleet of LWR’s are approaching the end of their original 40 year licenses. Most of these have applied for and been granted… (more)

Subjects/Keywords: MTR; SFR; MgO; reflector; SERPENT; LWRS; Advanced Reactors; Generation IV; test assembly; test assemblies

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APA (6th Edition):

Scherr, J. B. (2016). Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156894

Chicago Manual of Style (16th Edition):

Scherr, Jonathan B. “Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D.” 2016. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/156894.

MLA Handbook (7th Edition):

Scherr, Jonathan B. “Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D.” 2016. Web. 13 Apr 2021.

Vancouver:

Scherr JB. Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/156894.

Council of Science Editors:

Scherr JB. Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/156894


Texas A&M University

2. Cuvelier, Marie-Hermine. Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 Minimization of HLW inventories and U consumption are key elements guaranteeing nuclear energy expansion. The integration of complex nuclear systems into a viable cycle yet… (more)

Subjects/Keywords: TRU transmutation; TRU elimination; fission spectrum discrepancies; fission spectrum uncertainties impact on fuel cycle parameters; AP1000-VHTR fuel cycle; Thorium; ThO2

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APA (6th Edition):

Cuvelier, M. (2012). Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984

Chicago Manual of Style (16th Edition):

Cuvelier, Marie-Hermine. “Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984.

MLA Handbook (7th Edition):

Cuvelier, Marie-Hermine. “Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties.” 2012. Web. 13 Apr 2021.

Vancouver:

Cuvelier M. Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984.

Council of Science Editors:

Cuvelier M. Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984


Texas A&M University

3. Marcantel, Grace Ann. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.

Degree: MS, Nuclear Engineering, 2018, Texas A&M University

 The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advanced reactor designs in the generation IV class. Advanced reactors operate in more… (more)

Subjects/Keywords: TRIGA; FHR; VHTR; energy spectrum; MCNP; similarity factors

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APA (6th Edition):

Marcantel, G. A. (2018). Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173485

Chicago Manual of Style (16th Edition):

Marcantel, Grace Ann. “Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.” 2018. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/173485.

MLA Handbook (7th Edition):

Marcantel, Grace Ann. “Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.” 2018. Web. 13 Apr 2021.

Vancouver:

Marcantel GA. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/173485.

Council of Science Editors:

Marcantel GA. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173485


Texas A&M University

4. Kang, Changwoo. Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe.

Degree: PhD, Nuclear Engineering, 2018, Texas A&M University

 Irradiation of the materials with neutrons or energetic particles creates a significant number of point defects and nucleates extended defects, such as dislocations and voids.… (more)

Subjects/Keywords: Molecular dynamics; Strain; Displacement cascade; Nano-indentation

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APA (6th Edition):

Kang, C. (2018). Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173306

Chicago Manual of Style (16th Edition):

Kang, Changwoo. “Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe.” 2018. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/173306.

MLA Handbook (7th Edition):

Kang, Changwoo. “Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe.” 2018. Web. 13 Apr 2021.

Vancouver:

Kang C. Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/173306.

Council of Science Editors:

Kang C. Atomic Scale Studies of the Stress Effects on Defect Kinetics and Damage Evolution of Irradiated Fe. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173306


Texas A&M University

5. Scherr, Jonathan B. A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints.

Degree: PhD, Nuclear Engineering, 2018, Texas A&M University

 A novel hierarchical heuristic engineering design method is developed that is based on levels of abstraction. This was created in response to the dearth of… (more)

Subjects/Keywords: Engineering design; nuclear

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APA (6th Edition):

Scherr, J. B. (2018). A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173968

Chicago Manual of Style (16th Edition):

Scherr, Jonathan B. “A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints.” 2018. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/173968.

MLA Handbook (7th Edition):

Scherr, Jonathan B. “A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints.” 2018. Web. 13 Apr 2021.

Vancouver:

Scherr JB. A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/173968.

Council of Science Editors:

Scherr JB. A Hierarchical Heuristic Engineering Design Method for Nuclear Systems Based On the Progressive Definition of Constraints. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173968


Texas A&M University

6. Yancey, Kristina. Nationwide Used Fuel Inventory Analysis.

Degree: MS, Nuclear Engineering, 2013, Texas A&M University

 The goal of this research was to develop a methodology to collect inventory estimates for the analysis and characterization of used fuel in the United… (more)

Subjects/Keywords: nuclear; energy; spent fuel; used fuel; nuclide inventories; PWR; BWR; applicability range

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APA (6th Edition):

Yancey, K. (2013). Nationwide Used Fuel Inventory Analysis. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151866

Chicago Manual of Style (16th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/151866.

MLA Handbook (7th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Web. 13 Apr 2021.

Vancouver:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/151866.

Council of Science Editors:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151866


Texas A&M University

7. Hearne, Jason A. Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator.

Degree: MS, Nuclear Engineering, 2015, Texas A&M University

 The aim of this study is to analyze the transmutation of Long Lived Fission Products (LLFPs) using an accelerator based system. The seven LLFP’s are… (more)

Subjects/Keywords: Technetium; transmutation; accelerator transmutation; cross sections

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APA (6th Edition):

Hearne, J. A. (2015). Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/154964

Chicago Manual of Style (16th Edition):

Hearne, Jason A. “Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator.” 2015. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/154964.

MLA Handbook (7th Edition):

Hearne, Jason A. “Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator.” 2015. Web. 13 Apr 2021.

Vancouver:

Hearne JA. Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/154964.

Council of Science Editors:

Hearne JA. Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/154964


Texas A&M University

8. Gitau, Ernest Travis Ngure. Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 Pebble-fueled high temperature gas-cooled reactor (HTGR) technology was first developed by the Federal Republic of Germany in the 1950s. More recently, the design has been… (more)

Subjects/Keywords: non-proliferation; PBMR; pebble bed; nuclear safeguards; nonproliferation

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APA (6th Edition):

Gitau, E. T. N. (2012). Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2011-08-9868

Chicago Manual of Style (16th Edition):

Gitau, Ernest Travis Ngure. “Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2011-08-9868.

MLA Handbook (7th Edition):

Gitau, Ernest Travis Ngure. “Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor.” 2012. Web. 13 Apr 2021.

Vancouver:

Gitau ETN. Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-08-9868.

Council of Science Editors:

Gitau ETN. Development and Evaluation of a Safeguards System Concept for a Pebble-Fueled High Temperature Gas-cooled Reactor. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-08-9868


Texas A&M University

9. Kitcher, Evans Damenortey, 1987-. Performance and Safety Analysis of a Generic Small Modular Reactor.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 The high and ever growing demand for electricity coupled with environmental concerns and a worldwide desire to shed petroleum dependence, all point to a shift… (more)

Subjects/Keywords: Assessment; Proliferation Resistance; Single Channel Analysis; Neutronics Analysis; Water Reactor; Integral Pressurized; Small Modular Reactor

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APA (6th Edition):

Kitcher, Evans Damenortey, 1. (2012). Performance and Safety Analysis of a Generic Small Modular Reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148135

Chicago Manual of Style (16th Edition):

Kitcher, Evans Damenortey, 1987-. “Performance and Safety Analysis of a Generic Small Modular Reactor.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/148135.

MLA Handbook (7th Edition):

Kitcher, Evans Damenortey, 1987-. “Performance and Safety Analysis of a Generic Small Modular Reactor.” 2012. Web. 13 Apr 2021.

Vancouver:

Kitcher, Evans Damenortey 1. Performance and Safety Analysis of a Generic Small Modular Reactor. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/148135.

Council of Science Editors:

Kitcher, Evans Damenortey 1. Performance and Safety Analysis of a Generic Small Modular Reactor. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148135


Texas A&M University

10. Lakshmipathy, Sathish Kumar. VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 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)

Subjects/Keywords: Particle Swarm Optimization; Core shuffling optimization

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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 April 13, 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. 13 Apr 2021.

Vancouver:

Lakshmipathy SK. VHTR Core Shuffling Algorithm Using Particle Swarm Optimization ReloPSO-3D. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. 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

11. Zhang, Yunhuang. Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies.

Degree: MS, Nuclear Engineering, 2011, Texas A&M University

 The accumulation of spent nuclear fuel may be hindering the expansion of nuclear electricity production. However, the reprocessing and recycling of spent fuel may reduce… (more)

Subjects/Keywords: Transuranics Transmutation; Nuclear Fuel Multi-Recycling; Advanced MOX; IMF; Fuel Assembly; Long-term Radiotoxicity; Long-term Decay Heat; Americium Coating

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APA (6th Edition):

Zhang, Y. (2011). Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7470

Chicago Manual of Style (16th Edition):

Zhang, Yunhuang. “Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies.” 2011. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7470.

MLA Handbook (7th Edition):

Zhang, Yunhuang. “Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies.” 2011. Web. 13 Apr 2021.

Vancouver:

Zhang Y. Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies. [Internet] [Masters thesis]. Texas A&M University; 2011. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7470.

Council of Science Editors:

Zhang Y. Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies. [Masters Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7470


Texas A&M University

12. Guy, Troy Lamar. Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications.

Degree: MS, Nuclear Engineering, 2011, Texas A&M University

 The present study is focused on evaluating higher actinides beyond uranium that are capable of supporting power and propulsion requirements in robotic deep space and… (more)

Subjects/Keywords: actinide; deep space; propulsion; americium; fission; fission fragments

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APA (6th Edition):

Guy, T. L. (2011). Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7416

Chicago Manual of Style (16th Edition):

Guy, Troy Lamar. “Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications.” 2011. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7416.

MLA Handbook (7th Edition):

Guy, Troy Lamar. “Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications.” 2011. Web. 13 Apr 2021.

Vancouver:

Guy TL. Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications. [Internet] [Masters thesis]. Texas A&M University; 2011. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7416.

Council of Science Editors:

Guy TL. Analysis of Advanced Actinide-Fueled Energy Systems for Deep Space Propulsion Applications. [Masters Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7416


Texas A&M University

13. Lane, Taylor K. Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models.

Degree: MS, Nuclear Engineering, 2015, Texas A&M University

 A common method to solving coupled radiation-hydrodynamics simulations is to use the Implicit Monte Carlo method as the radiation solve and the BHR-2 mix model… (more)

Subjects/Keywords: Monte Carlo; Radiation Hydrodynamics; mix

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APA (6th Edition):

Lane, T. K. (2015). Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156162

Chicago Manual of Style (16th Edition):

Lane, Taylor K. “Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models.” 2015. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/156162.

MLA Handbook (7th Edition):

Lane, Taylor K. “Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models.” 2015. Web. 13 Apr 2021.

Vancouver:

Lane TK. Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/156162.

Council of Science Editors:

Lane TK. Energy Density Gradient Estimation for Monte Carlo Methods in Mix Models. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/156162


Texas A&M University

14. Abdoelatef, Mohammed G. MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS.

Degree: MS, Nuclear Engineering, 2019, Texas A&M University

 A phase field model was developed to simulate the grain refinement in solids. The model considers the interfacial energies of grain boundaries and bubble surfaces,… (more)

Subjects/Keywords: grain refinement; recrystallization; particle stimulate nucleation; HBS; phase field; UOv2; UMo

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APA (6th Edition):

Abdoelatef, M. G. (2019). MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/188702

Chicago Manual of Style (16th Edition):

Abdoelatef, Mohammed G. “MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS.” 2019. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/188702.

MLA Handbook (7th Edition):

Abdoelatef, Mohammed G. “MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS.” 2019. Web. 13 Apr 2021.

Vancouver:

Abdoelatef MG. MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS. [Internet] [Masters thesis]. Texas A&M University; 2019. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/188702.

Council of Science Editors:

Abdoelatef MG. MESOSCALE MODELING OF GRAIN REFINEMENT IN SOLIDS. [Masters Thesis]. Texas A&M University; 2019. Available from: http://hdl.handle.net/1969.1/188702


Texas A&M University

15. Kang, Hyun Hee. Machine Learning Implementation in Radiative Properties Prediction for Porous Media.

Degree: MS, Mechanical Engineering, 2019, Texas A&M University

 Predicting the radiative properties of porous media is highly important in many engineering applications (e.g. additive manufacturing). The radiative properties of packed beds highly depend… (more)

Subjects/Keywords: Radiative heat transfer; Porous media

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APA (6th Edition):

Kang, H. H. (2019). Machine Learning Implementation in Radiative Properties Prediction for Porous Media. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/188755

Chicago Manual of Style (16th Edition):

Kang, Hyun Hee. “Machine Learning Implementation in Radiative Properties Prediction for Porous Media.” 2019. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/188755.

MLA Handbook (7th Edition):

Kang, Hyun Hee. “Machine Learning Implementation in Radiative Properties Prediction for Porous Media.” 2019. Web. 13 Apr 2021.

Vancouver:

Kang HH. Machine Learning Implementation in Radiative Properties Prediction for Porous Media. [Internet] [Masters thesis]. Texas A&M University; 2019. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/188755.

Council of Science Editors:

Kang HH. Machine Learning Implementation in Radiative Properties Prediction for Porous Media. [Masters Thesis]. Texas A&M University; 2019. Available from: http://hdl.handle.net/1969.1/188755


Texas A&M University

16. Al Rashdan, Ahmad Y. M. Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions.

Degree: PhD, Nuclear Engineering, 2014, Texas A&M University

 The complex and coupled behavior of variables in the currently developing Generation IV reactors and Small Modular Reactors is becoming a major incentive to seek… (more)

Subjects/Keywords: nuclear reactors design; SMR design; complex systems evaluation; screening; sensitivity analysis; variables effects; variables decoupling; variables interactions; adaptive design exploration

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APA (6th Edition):

Al Rashdan, A. Y. M. (2014). Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/154031

Chicago Manual of Style (16th Edition):

Al Rashdan, Ahmad Y M. “Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions.” 2014. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/154031.

MLA Handbook (7th Edition):

Al Rashdan, Ahmad Y M. “Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions.” 2014. Web. 13 Apr 2021.

Vancouver:

Al Rashdan AYM. Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions. [Internet] [Doctoral dissertation]. Texas A&M University; 2014. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/154031.

Council of Science Editors:

Al Rashdan AYM. Novel Evaluation Methods for Complex Systems via Adaptive Sequential Exploration of Variables Interactions. [Doctoral Dissertation]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/154031


Texas A&M University

17. Ahn, Sangjoon. Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects.

Degree: PhD, Nuclear Engineering, 2013, Texas A&M University

 Uranium-zirconium (U-Zr) alloys comprise a class of metallic nuclear fuel that is regularly considered for application in fast nuclear energy systems. The U-10wt%Zr alloy has… (more)

Subjects/Keywords: Uranium; zirconium; U-Zr alloy; metal fuel performance; fission gas swelling; gas bubble nucleation; ion-beam irradiation; metallurgy; nanostructure; phase transformation; phase diagram; electron diffraction; in-situ heated TEM

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APA (6th Edition):

Ahn, S. (2013). Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151201

Chicago Manual of Style (16th Edition):

Ahn, Sangjoon. “Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects.” 2013. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/151201.

MLA Handbook (7th Edition):

Ahn, Sangjoon. “Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects.” 2013. Web. 13 Apr 2021.

Vancouver:

Ahn S. Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects. [Internet] [Doctoral dissertation]. Texas A&M University; 2013. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/151201.

Council of Science Editors:

Ahn S. Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects. [Doctoral Dissertation]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151201


Texas A&M University

18. Frisani, Angelo. Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools.

Degree: MS, Nuclear Engineering, 2011, Texas A&M University

 The design of passive heat removal systems is one of the main concerns for the modular Very High Temperature Gas-Cooled Reactors (VHTR) vessel cavity. The… (more)

Subjects/Keywords: Turbulence; buoyancy; convection; RCCS; CFD; VHTR

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APA (6th Edition):

Frisani, A. (2011). Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-7767

Chicago Manual of Style (16th Edition):

Frisani, Angelo. “Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools.” 2011. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-7767.

MLA Handbook (7th Edition):

Frisani, Angelo. “Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools.” 2011. Web. 13 Apr 2021.

Vancouver:

Frisani A. Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools. [Internet] [Masters thesis]. Texas A&M University; 2011. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-7767.

Council of Science Editors:

Frisani A. Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools. [Masters Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-7767


Texas A&M University

19. Ames, David E. High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source.

Degree: PhD, Nuclear Engineering, 2011, Texas A&M University

 A new high-fidelity integrated system method and analysis approach was developed and implemented for consistent and comprehensive evaluations of advanced fuel cycles leading to minimized… (more)

Subjects/Keywords: Nuclear; Optimization; VHTR; AP100; Recycle; Environment; Sensitivity; TRU

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APA (6th Edition):

Ames, D. E. (2011). High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549

Chicago Manual of Style (16th Edition):

Ames, David E. “High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source.” 2011. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549.

MLA Handbook (7th Edition):

Ames, David E. “High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source.” 2011. Web. 13 Apr 2021.

Vancouver:

Ames DE. High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source. [Internet] [Doctoral dissertation]. Texas A&M University; 2011. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549.

Council of Science Editors:

Ames DE. High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source. [Doctoral Dissertation]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549


Texas A&M University

20. Rosaire IV, Carol Gwyn. Anisotropic Neutron Imaging.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

 Anisotropic neutron imaging presents a unique method to process images in order to produce a human-readable, singular, isotropic image from a set of anisotropic neutron… (more)

Subjects/Keywords: anisotropic; neutron; imaging; radiography; discrete wavelet transform; slit collimator

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APA (6th Edition):

Rosaire IV, C. G. (2016). Anisotropic Neutron Imaging. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156979

Chicago Manual of Style (16th Edition):

Rosaire IV, Carol Gwyn. “Anisotropic Neutron Imaging.” 2016. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/156979.

MLA Handbook (7th Edition):

Rosaire IV, Carol Gwyn. “Anisotropic Neutron Imaging.” 2016. Web. 13 Apr 2021.

Vancouver:

Rosaire IV CG. Anisotropic Neutron Imaging. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/156979.

Council of Science Editors:

Rosaire IV CG. Anisotropic Neutron Imaging. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/156979


Texas A&M University

21. Kelly, Ryan Patrick. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.

Degree: MS, Nuclear Engineering, 2013, Texas A&M University

 The objective of this thesis is to quantify the uncertainty in radiation dose rate estimates outside of a used fuel dry cask storage unit due… (more)

Subjects/Keywords: concrete; shielding; composition; dry cask storage

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APA (6th Edition):

Kelly, R. P. (2013). Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158896

Chicago Manual of Style (16th Edition):

Kelly, Ryan Patrick. “Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.” 2013. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/158896.

MLA Handbook (7th Edition):

Kelly, Ryan Patrick. “Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.” 2013. Web. 13 Apr 2021.

Vancouver:

Kelly RP. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/158896.

Council of Science Editors:

Kelly RP. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/158896


Texas A&M University

22. Worn, Cheyn. An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 Shadow shielding is a novel and practical concept for waste heat rejection from lunar surface spacecraft systems. A shadow shield is a light shield that… (more)

Subjects/Keywords: Space Nuclear Systems; Heat Radiators; Thermal Analysis; Parabolic Shadow Shielding; Lunar Thermal Environment; SAFE-400; Radiative Heat Transfer; Carnot Cycle

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APA (6th Edition):

Worn, C. (2012). An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11202

Chicago Manual of Style (16th Edition):

Worn, Cheyn. “An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11202.

MLA Handbook (7th Edition):

Worn, Cheyn. “An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection.” 2012. Web. 13 Apr 2021.

Vancouver:

Worn C. An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11202.

Council of Science Editors:

Worn C. An Evaluation of Shadow Shielding for Lunar System Waste Heat Rejection. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11202


Texas A&M University

23. Chen, Tianyi. Radiation Response of Oxide Dispersion Strengthened Alloy.

Degree: PhD, Nuclear Engineering, 2015, Texas A&M University

 Ferritic-martensitic (F/M) steels are known to have greater resistance to void swelling, higher thermal conductivities and lower thermal expansion coefficients than austenitic steels do. The… (more)

Subjects/Keywords: ODS; radiation response; F/M steel; swelling; oxide dispersion strengthened

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APA (6th Edition):

Chen, T. (2015). Radiation Response of Oxide Dispersion Strengthened Alloy. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156414

Chicago Manual of Style (16th Edition):

Chen, Tianyi. “Radiation Response of Oxide Dispersion Strengthened Alloy.” 2015. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/156414.

MLA Handbook (7th Edition):

Chen, Tianyi. “Radiation Response of Oxide Dispersion Strengthened Alloy.” 2015. Web. 13 Apr 2021.

Vancouver:

Chen T. Radiation Response of Oxide Dispersion Strengthened Alloy. [Internet] [Doctoral dissertation]. Texas A&M University; 2015. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/156414.

Council of Science Editors:

Chen T. Radiation Response of Oxide Dispersion Strengthened Alloy. [Doctoral Dissertation]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/156414


Texas A&M University

24. Huang, Guan. Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts.

Degree: PhD, Mechanical Engineering, 2018, Texas A&M University

 Finding replacements for R-410A is paramount, and it primarily focuses on issues such as energy efficiency, GWP, flammability, toxicity, and safety. The study reported herein… (more)

Subjects/Keywords: Outdoor dry-bulb temperature; Relative humidity; Weighting factor; Cooling Season; Vapor compression system; Evaporative cooling; Optimization; Modeling; R410A; HRV; ERV; DOAS; Internal Heat Exchanger; Subcooling; Superheated

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APA (6th Edition):

Huang, G. (2018). Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174457

Chicago Manual of Style (16th Edition):

Huang, Guan. “Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts.” 2018. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/174457.

MLA Handbook (7th Edition):

Huang, Guan. “Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts.” 2018. Web. 13 Apr 2021.

Vancouver:

Huang G. Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/174457.

Council of Science Editors:

Huang G. Improving Vapor Compression Cycle Efficiencies in Support of Conventional Refrigerant Phaseouts. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174457


Texas A&M University

25. Hawila, Mohammad Abdel Majid Mustafa. Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling.

Degree: PhD, Nuclear Engineering, 2018, Texas A&M University

 The Reactor Core Isolation Cooling (RCIC) System is a safety system that provides water to the reactor pressure vessel during off-normal Boiling Water Reactor (BWR)… (more)

Subjects/Keywords: Scaling; severe accident; CFD; safety; Nuclear; BWR; Similarity; Turbine; pool; Fukushima; turbo-machinery

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APA (6th Edition):

Hawila, M. A. M. M. (2018). Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174514

Chicago Manual of Style (16th Edition):

Hawila, Mohammad Abdel Majid Mustafa. “Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling.” 2018. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/174514.

MLA Handbook (7th Edition):

Hawila, Mohammad Abdel Majid Mustafa. “Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling.” 2018. Web. 13 Apr 2021.

Vancouver:

Hawila MAMM. Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling. [Internet] [Doctoral dissertation]. Texas A&M University; 2018. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/174514.

Council of Science Editors:

Hawila MAMM. Novel Similarity Level Characterization Methodology Informed by CFD for RCIC System Scaling. [Doctoral Dissertation]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/174514


Texas A&M University

26. Kennas, Miltiadis Demetrios. Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels.

Degree: PhD, Nuclear Engineering, 2020, Texas A&M University

 This study is a systematic investigation on the interface reactions of various coating materials for nuclear fuel cladding. In particular this study focused on metallic… (more)

Subjects/Keywords: Accident Tolerant Fuels; Zircaloy-4; Coated Zircaloy; Fuel Cladding; Cold-Spraying; MAX Phase; Ti2AlC; FeCrAl; Pure Cr; Fe70Cr20Al10; Ion Irradiation; Intermetallics; Intermetallic; Metallic Interdiffusion

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APA (6th Edition):

Kennas, M. D. (2020). Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/191709

Chicago Manual of Style (16th Edition):

Kennas, Miltiadis Demetrios. “Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels.” 2020. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/191709.

MLA Handbook (7th Edition):

Kennas, Miltiadis Demetrios. “Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels.” 2020. Web. 13 Apr 2021.

Vancouver:

Kennas MD. Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels. [Internet] [Doctoral dissertation]. Texas A&M University; 2020. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/191709.

Council of Science Editors:

Kennas MD. Investigating Fuel Cladding Coating Materials for Accident Tolerant Fuels. [Doctoral Dissertation]. Texas A&M University; 2020. Available from: http://hdl.handle.net/1969.1/191709


Texas A&M University

27. Kumar, Akansha. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

 The optimization of a complex system involves the determination of optimum values for a set of design parameters. The optimization search happens in order to… (more)

Subjects/Keywords: genetic algorithms; optimization; nuclear; reactor

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APA (6th Edition):

Kumar, A. (2016). An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/159121

Chicago Manual of Style (16th Edition):

Kumar, Akansha. “An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.” 2016. Doctoral Dissertation, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/159121.

MLA Handbook (7th Edition):

Kumar, Akansha. “An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.” 2016. Web. 13 Apr 2021.

Vancouver:

Kumar A. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/159121.

Council of Science Editors:

Kumar A. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/159121

28. Moo, Jee Hoon. Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments.

Degree: MS, Nuclear Engineering, 2019, Texas A&M University

 The objective of this study is to predict the damage that could be created on a reinforced concrete wall due to the impact of Tri-Nitro… (more)

Subjects/Keywords: Impact Investigation; ANSYS AUTODYN; Reinforced Concrete Model; TNT Shaped Charge; Vulnerability; Hypothetical Nuclear Research Reactor Facility; Physical Protection System (PPS); Adversary Sequence Diagram (ASD); Estimate of Adversary Sequence Interruption (EASI); Probability of Interruption (PI)

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APA (6th Edition):

Moo, J. H. (2019). Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/185059

Chicago Manual of Style (16th Edition):

Moo, Jee Hoon. “Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments.” 2019. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/185059.

MLA Handbook (7th Edition):

Moo, Jee Hoon. “Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments.” 2019. Web. 13 Apr 2021.

Vancouver:

Moo JH. Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments. [Internet] [Masters thesis]. Texas A&M University; 2019. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/185059.

Council of Science Editors:

Moo JH. Impact Investigation Using Ansys Autodyn Code on a Reinforced Concrete Model Due To TNT Shaped Charge for Nuclear Security Vulnerability Assessments. [Masters Thesis]. Texas A&M University; 2019. Available from: http://hdl.handle.net/1969.1/185059

29. Leimon, Michael 1985-. Coupling Interface for Physics-to-System Simulations.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 A new interfacial code was developed to couple the reactor physics code PARCS/AGREE to the systems level code MELCOR, with a goal of enabling state-… (more)

Subjects/Keywords: MELCOR; AGREE; PARCS; coupling interface; coupling code; simulation coupling; coupling; NGNP; PBMR400; nuclear engineering

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APA (6th Edition):

Leimon, M. 1. (2012). Coupling Interface for Physics-to-System Simulations. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148367

Chicago Manual of Style (16th Edition):

Leimon, Michael 1985-. “Coupling Interface for Physics-to-System Simulations.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/148367.

MLA Handbook (7th Edition):

Leimon, Michael 1985-. “Coupling Interface for Physics-to-System Simulations.” 2012. Web. 13 Apr 2021.

Vancouver:

Leimon M1. Coupling Interface for Physics-to-System Simulations. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/148367.

Council of Science Editors:

Leimon M1. Coupling Interface for Physics-to-System Simulations. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148367

30. Rodi, Paul J. Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 This thesis involves exploring enhancement of estimating the probability of a critical station blackout in nuclear power plant operations by the use of direct numerical… (more)

Subjects/Keywords: PRA; Loop; Commercial Nuclear Power Plants; STP-TAMIL; SBO; CSBO; STPNOC; MATLAB; Non-Recovery Integral; Recovery

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APA (6th Edition):

Rodi, P. J. (2012). Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11145

Chicago Manual of Style (16th Edition):

Rodi, Paul J. “Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout.” 2012. Masters Thesis, Texas A&M University. Accessed April 13, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11145.

MLA Handbook (7th Edition):

Rodi, Paul J. “Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout.” 2012. Web. 13 Apr 2021.

Vancouver:

Rodi PJ. Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Apr 13]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11145.

Council of Science Editors:

Rodi PJ. Algorithms for Incorporation of Dynamic Recovery in Estimating Frequency of Critical Station Blackout. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-11145

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