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You searched for +publisher:"Texas A&M University" +contributor:("McDeavitt, Sean M"). Showing records 1 – 30 of 38 total matches.

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Texas A&M University

1. Garnetti, David J. Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications.

Degree: 2010, Texas A&M University

 The research in this thesis covers the design and implementation of a depleted uranium (DU) powder production system and the initial results of a DU-Zr-Mg… (more)

Subjects/Keywords: Uranium; Hydride; Alpha Phase; Sintering; Powder Production; Dehydride; Fuel

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APA (6th Edition):

Garnetti, D. J. (2010). Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7382

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Garnetti, David J. “Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications.” 2010. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7382.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Garnetti, David J. “Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications.” 2010. Web. 16 Feb 2019.

Vancouver:

Garnetti DJ. Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7382.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Garnetti DJ. Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7382

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

2. 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 February 16, 2019. 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. 16 Feb 2019.

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 2019 Feb 16]. 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

3. Smith, Joshua 1987-. Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses.

Degree: 2012, Texas A&M University

 The objective of this work was to continue the evaluation of the high thermal conductivity UO2-BeO (UBO) nuclear fuel. Current ceramic UO2 fuel offers many… (more)

Subjects/Keywords: Levelized Fuel Cost BeO Nuclear Fuel; Nuclear Core Simulations; BeO Enhanced Conductivity Fuel; Beryllium Oxide Nuclear Fuel

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APA (6th Edition):

Smith, J. 1. (2012). Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156356

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Smith, Joshua 1987-. “Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/156356.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Smith, Joshua 1987-. “Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses.” 2012. Web. 16 Feb 2019.

Vancouver:

Smith J1. Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/156356.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Smith J1. Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/156356

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

4. Garcia, Chad. Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix.

Degree: 2014, Texas A&M University

 The primary fuel used in light water nuclear reactors (LWRs) is uranium dioxide (UO2), which has a low thermal conductivity that causes a large thermal… (more)

Subjects/Keywords: Beryllium Oxide; Uranium Dioxide; Thermal Conductivity; Sintering; Oxide Fuel; Light Water Reactor

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APA (6th Edition):

Garcia, C. (2014). Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158902

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Garcia, Chad. “Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix.” 2014. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/158902.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Garcia, Chad. “Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix.” 2014. Web. 16 Feb 2019.

Vancouver:

Garcia C. Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix. [Internet] [Thesis]. Texas A&M University; 2014. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/158902.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Garcia C. Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix. [Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/158902

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

5. Mews, Paul Aaron. Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form.

Degree: 2009, Texas A&M University

 Stainless steel ? zirconium alloys were developed by the US Department of Energy Laboratories as metallic waste forms for noble metal fission products. This thesis… (more)

Subjects/Keywords: Technetium; Metal Waste Form; Iron-Zirconium; AFCI; nuclear waste

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APA (6th Edition):

Mews, P. A. (2009). Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2092

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Mews, Paul Aaron. “Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form.” 2009. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2092.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Mews, Paul Aaron. “Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form.” 2009. Web. 16 Feb 2019.

Vancouver:

Mews PA. Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form. [Internet] [Thesis]. Texas A&M University; 2009. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2092.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Mews PA. Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form. [Thesis]. Texas A&M University; 2009. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2092

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

6. Parkison, Adam Joseph. Hydride production in zircaloy-4 as a function of time and temperature.

Degree: 2009, Texas A&M University

 The experiments performed for this thesis were designed to define the primary process variables of time, temperature, and atmosphere for an engineering system that will… (more)

Subjects/Keywords: hydride; zirconium; zircaloy; cladding; nuclear; reprocess

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APA (6th Edition):

Parkison, A. J. (2009). Hydride production in zircaloy-4 as a function of time and temperature. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2788

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Parkison, Adam Joseph. “Hydride production in zircaloy-4 as a function of time and temperature.” 2009. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2788.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Parkison, Adam Joseph. “Hydride production in zircaloy-4 as a function of time and temperature.” 2009. Web. 16 Feb 2019.

Vancouver:

Parkison AJ. Hydride production in zircaloy-4 as a function of time and temperature. [Internet] [Thesis]. Texas A&M University; 2009. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2788.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Parkison AJ. Hydride production in zircaloy-4 as a function of time and temperature. [Thesis]. Texas A&M University; 2009. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2788

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

7. Hogelin, Thomas Russell. Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.

Degree: 2011, Texas A&M University

 The reprocessing of used nuclear fuel requires the dissolution and separation of numerous radioisotopes that are present as fission products in the fuel. The leading… (more)

Subjects/Keywords: nuclear; fuel; reprocessing; UREX; radioactive; HRGS

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APA (6th Edition):

Hogelin, T. R. (2011). Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Hogelin, Thomas Russell. “Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.” 2011. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Hogelin, Thomas Russell. “Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.” 2011. Web. 16 Feb 2019.

Vancouver:

Hogelin TR. Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. [Internet] [Thesis]. Texas A&M University; 2011. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Hogelin TR. Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. [Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

8. Feener, Jessica S. Safeguards for Uranium Extraction (UREX) +1a Process.

Degree: 2011, Texas A&M University

 As nuclear energy grows in the United States and around the world, the expansion of the nuclear fuel cycle is inevitable. All currently deployed commercial… (more)

Subjects/Keywords: nuclear material safeguards; UREX; UREX+1a; Uranium Extraction; proliferation resistant; proliferation resistance; reprocessing; PUREX; Plutonium; Uranium; IAEA; TMFD; Tension Metastable Fluid Detector; detection probability; nondetection probability; non-detection probability; nuclear material accountancy; containment and surveillance; solution monitoring; process monitoring; false alarm probability; real-time measurement; material balance area; material balance period; key measurement point; significant quantity; timely detection; defense in depth; detector; non-destructive assay; NDA; front-end measurement; material unaccounted for; CCD-PEG; TRUEX; TALSPEAK

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APA (6th Edition):

Feener, J. S. (2011). Safeguards for Uranium Extraction (UREX) +1a Process. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Feener, Jessica S. “Safeguards for Uranium Extraction (UREX) +1a Process.” 2011. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Feener, Jessica S. “Safeguards for Uranium Extraction (UREX) +1a Process.” 2011. Web. 16 Feb 2019.

Vancouver:

Feener JS. Safeguards for Uranium Extraction (UREX) +1a Process. [Internet] [Thesis]. Texas A&M University; 2011. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Feener JS. Safeguards for Uranium Extraction (UREX) +1a Process. [Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-05-270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

9. Hausaman, Jeffrey Stephen. Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors.

Degree: 2012, Texas A&M University

 The development of fast reactor systems capable of burning recycled transuranic (TRU) isotopes has been underway for decades at various levels of activity. These systems… (more)

Subjects/Keywords: Extrusion; Uranium; Zirconium; Transuranics

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APA (6th Edition):

Hausaman, J. S. (2012). Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10609

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Hausaman, Jeffrey Stephen. “Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10609.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Hausaman, Jeffrey Stephen. “Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors.” 2012. Web. 16 Feb 2019.

Vancouver:

Hausaman JS. Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10609.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Hausaman JS. Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2011-12-10609

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

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

Degree: 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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Cuvelier, Marie-Hermine. “Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Cuvelier, Marie-Hermine. “Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties.” 2012. Web. 16 Feb 2019.

Vancouver:

Cuvelier M. Advanced Fuel Cycle Scenarios with AP1000 PWRs and VHTRs and Fission Spectrum Uncertainties. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10984.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

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

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

11. Wegener, Jeffrey J. Production of cerium oxide microsheres by an internal gelation sol-gel process.

Degree: 2010, Texas A&M University

 The experiments performed for this research were completed to produce solid cerium oxide microspheres by an internal gelation sol-gel process. The motivation for this work… (more)

Subjects/Keywords: Internal Gelation Sol-Gel; Microspheres; Cerium Oxide

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APA (6th Edition):

Wegener, J. J. (2010). Production of cerium oxide microsheres by an internal gelation sol-gel process. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2008-12-83

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Wegener, Jeffrey J. “Production of cerium oxide microsheres by an internal gelation sol-gel process.” 2010. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2008-12-83.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Wegener, Jeffrey J. “Production of cerium oxide microsheres by an internal gelation sol-gel process.” 2010. Web. 16 Feb 2019.

Vancouver:

Wegener JJ. Production of cerium oxide microsheres by an internal gelation sol-gel process. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2008-12-83.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wegener JJ. Production of cerium oxide microsheres by an internal gelation sol-gel process. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2008-12-83

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

12. Thompson, Chad 1984-. A Rotating Electrode System for the Generation of Metal Alloy Microspheres.

Degree: 2012, Texas A&M University

 TerraPower LLC is designing a fast breed and burn reactor intended to operate for up to 40 years without refueling, designated as the Travelling Wave… (more)

Subjects/Keywords: Powder Metallurgy; Metallic Powder; Rotating Electrode; RES; REP

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APA (6th Edition):

Thompson, C. 1. (2012). A Rotating Electrode System for the Generation of Metal Alloy Microspheres. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148295

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Thompson, Chad 1984-. “A Rotating Electrode System for the Generation of Metal Alloy Microspheres.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/148295.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Thompson, Chad 1984-. “A Rotating Electrode System for the Generation of Metal Alloy Microspheres.” 2012. Web. 16 Feb 2019.

Vancouver:

Thompson C1. A Rotating Electrode System for the Generation of Metal Alloy Microspheres. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/148295.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Thompson C1. A Rotating Electrode System for the Generation of Metal Alloy Microspheres. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148295

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

13. Mews, Kathryn Ann Wright. Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys.

Degree: 2013, Texas A&M University

 Uranium-zirconium alloy nuclear fuels have many advantages as compared with ceramic fuels, especially for fast reactor systems. However, metallic fuels aren?t currently used in commercial… (more)

Subjects/Keywords: uranium; zirconium; U-10wtZr; fission gas bubble; bubble formation; TEM; electropolish; implant; perchloric acid; he implant

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APA (6th Edition):

Mews, K. A. W. (2013). Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/149562

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Mews, Kathryn Ann Wright. “Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys.” 2013. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/149562.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Mews, Kathryn Ann Wright. “Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys.” 2013. Web. 16 Feb 2019.

Vancouver:

Mews KAW. Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/149562.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Mews KAW. Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/149562

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

14. Le Coq, Annabelle G. Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System.

Degree: 2013, Texas A&M University

 There has been a strong international interest in using pyroprocessing to close the fast nuclear reactor fuel cycle and reprocess spent fuel efficiently. To commercialize… (more)

Subjects/Keywords: Safeguards; Pyroprocessing; Neutron Resonance Densitometry

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APA (6th Edition):

Le Coq, A. G. (2013). Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151148

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Le Coq, Annabelle G. “Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System.” 2013. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/151148.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Le Coq, Annabelle G. “Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System.” 2013. Web. 16 Feb 2019.

Vancouver:

Le Coq AG. Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/151148.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Le Coq AG. Design of a Safeguards Instrument for Plutonium Quantification in an Electrochemical Refining System. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151148

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

15. Clemens, Jeffrey Tyler. Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation.

Degree: 2014, Texas A&M University

 The chemical effects of irradiation on high pressure methane and noble gas mixtures were investigated using gamma, electron beam, and neutron irradiation sources. The gamma… (more)

Subjects/Keywords: Methane; radiolysis; radiation chemistry; high pressure

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APA (6th Edition):

Clemens, J. T. (2014). Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/152836

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Clemens, Jeffrey Tyler. “Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation.” 2014. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/152836.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Clemens, Jeffrey Tyler. “Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation.” 2014. Web. 16 Feb 2019.

Vancouver:

Clemens JT. Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation. [Internet] [Thesis]. Texas A&M University; 2014. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/152836.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Clemens JT. Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation. [Thesis]. Texas A&M University; 2014. Available from: http://hdl.handle.net/1969.1/152836

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

16. Naramore, Michael J. High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication.

Degree: 2010, Texas A&M University

 The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxide (UO2) is a very effective nuclear fuel, but… (more)

Subjects/Keywords: Beryllium Oxide; BeO, High Thermal Conductivity; Neutronic

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APA (6th Edition):

Naramore, M. J. (2010). High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/153193

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Naramore, Michael J. “High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication.” 2010. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/153193.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Naramore, Michael J. “High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication.” 2010. Web. 16 Feb 2019.

Vancouver:

Naramore MJ. High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/153193.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Naramore MJ. High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/153193

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

17. Parkison, Adam J. Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process.

Degree: 2013, Texas A&M University

 The fundamental behavior underpinning a new processing concept was demonstrated which is capable of separating uranium from zirconium in U-Zr alloys through the formation and… (more)

Subjects/Keywords: Nuclear Pyroprocessing; Zirconium Uranium; Chlorine; Chlorination; Hydride Separation

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APA (6th Edition):

Parkison, A. J. (2013). Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/153202

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Parkison, Adam J. “Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process.” 2013. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/153202.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Parkison, Adam J. “Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process.” 2013. Web. 16 Feb 2019.

Vancouver:

Parkison AJ. Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/153202.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Parkison AJ. Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/153202

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

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

Degree: 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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/154964

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Hearne, Jason A. “Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator.” 2015. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/154964.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Hearne, Jason A. “Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator.” 2015. Web. 16 Feb 2019.

Vancouver:

Hearne JA. Analysis of the Transmutation of Long Lived Fission Products Using an Accelerator. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/154964.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

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

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

19. Hu, Liangfa. Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites.

Degree: 2015, Texas A&M University

 Advances in various aerospace and energy technologies call for new, multifunctional materials capable of operating under conditions that are challenging to the most advanced high-temperature… (more)

Subjects/Keywords: Composites; MAX phases; Shape memory alloys; Aluminum alloys

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APA (6th Edition):

Hu, L. (2015). Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155071

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Hu, Liangfa. “Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites.” 2015. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/155071.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Hu, Liangfa. “Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites.” 2015. Web. 16 Feb 2019.

Vancouver:

Hu L. Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/155071.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Hu L. Fabrication and Characterization of Interpenetrating Metal/Ternary Carbide Composites. [Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155071

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

20. Kulage, Zachary Andrew. Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting.

Degree: 2013, Texas A&M University

 Acts of terrorism and the use of explosives raise concerns about what can be done to prevent such acts. From stopping such a threat to… (more)

Subjects/Keywords: Neutron Activation Analysis; TRIGA; HFIR; Bateman Equation; Stable Isotopes

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APA (6th Edition):

Kulage, Z. A. (2013). Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156355

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kulage, Zachary Andrew. “Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting.” 2013. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/156355.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kulage, Zachary Andrew. “Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting.” 2013. Web. 16 Feb 2019.

Vancouver:

Kulage ZA. Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/156355.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kulage ZA. Encrypted Nanoparticles for Security, Counter-industrial Espionage, and Counterfeiting. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/156355

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

21. Kong, Tae Young. Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants.

Degree: 2016, Texas A&M University

 The U.S. Nuclear Regulatory Commission (NRC) is considering a revision of the existing system of radiation protection regulations with respect to ICRP Publication 103. It… (more)

Subjects/Keywords: Regulatory Science; Radiation Protection; Dose Constraint; Nuclear Power Plant

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APA (6th Edition):

Kong, T. Y. (2016). Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158101

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kong, Tae Young. “Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants.” 2016. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/158101.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kong, Tae Young. “Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants.” 2016. Web. 16 Feb 2019.

Vancouver:

Kong TY. Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants. [Internet] [Thesis]. Texas A&M University; 2016. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/158101.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kong TY. Regulatory Science and Radiation Protection: A Study of Dose Constraints for Members of the Public and Occupationally-exposed Workers at the U.S. Nuclear Power Plants. [Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/158101

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

22. Ortega, Luis H. Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste.

Degree: 2010, Texas A&M University

 The Advanced Fuel Cycle Initiative (AFCI) is a Department of Energy (DOE) program, that has been investigating technologies to improve fuel cycle sustainability and proliferation… (more)

Subjects/Keywords: radioactive; waste; cesium; strontium; bentonite; montmorillonite; ceramic

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APA (6th Edition):

Ortega, L. H. (2010). Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7548

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Ortega, Luis H. “Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste.” 2010. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7548.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ortega, Luis H. “Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste.” 2010. Web. 16 Feb 2019.

Vancouver:

Ortega LH. Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7548.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Ortega LH. Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-12-7548

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

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

Degree: 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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

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. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ames, David E. “High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source.” 2011. Web. 16 Feb 2019.

Vancouver:

Ames DE. High-Fidelity Nuclear Energy System Optimization towards an Environmentally Benign, Sustainable, and Secure Energy Source. [Internet] [Thesis]. Texas A&M University; 2011. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8549.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

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

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

24. Goddard, Braden. Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM.

Degree: 2013, Texas A&M University

 The ability of inspection agencies and facility operators to measure powders containing several actinides is increasingly necessary as new reprocessing techniques and fuel forms are… (more)

Subjects/Keywords: MCNPX; Neutron Multiplicity Counting; AWCC; ENMC; Point-model; Safeguards; Nonproliferation

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APA (6th Edition):

Goddard, B. (2013). Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/149361

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Goddard, Braden. “Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM.” 2013. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/149361.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Goddard, Braden. “Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM.” 2013. Web. 16 Feb 2019.

Vancouver:

Goddard B. Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/149361.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Goddard B. Quantitative NDA Measurements of Advanced Reprocessing Product Materials Containing U, NP, PU, and AM. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/149361

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

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

Degree: 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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151201

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

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. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/151201.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Ahn, Sangjoon. “Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects.” 2013. Web. 16 Feb 2019.

Vancouver:

Ahn S. Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/151201.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

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

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

26. Sames, William. Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties.

Degree: 2015, Texas A&M University

 Additive Manufacturing (AM) process parameters were studied for production of the high temperature alloy Inconel 718 using Electron Beam Melting (EBM) to better understand the… (more)

Subjects/Keywords: Additive Manufacturing; Inconel 718; review; electron beam melting; process parameters; grain growth; in situ heat treatment; mechanical properties

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APA (6th Edition):

Sames, W. (2015). Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155230

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Sames, William. “Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties.” 2015. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/155230.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Sames, William. “Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties.” 2015. Web. 16 Feb 2019.

Vancouver:

Sames W. Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/155230.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Sames W. Additive Manufacturing of Inconel 718 using Electron Beam Melting: Processing, Post-Processing, & Mechanical Properties. [Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155230

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


Texas A&M University

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

Degree: 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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156414

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Chen, Tianyi. “Radiation Response of Oxide Dispersion Strengthened Alloy.” 2015. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/156414.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Chen, Tianyi. “Radiation Response of Oxide Dispersion Strengthened Alloy.” 2015. Web. 16 Feb 2019.

Vancouver:

Chen T. Radiation Response of Oxide Dispersion Strengthened Alloy. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/156414.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

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

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

28. Kelley, Randy Dean. Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process.

Degree: 2011, Texas A&M University

 A process for recycling spent nuclear fuel cladding, a zirconium alloy (Zircaloy), into a metal powder that may be used for advanced nuclear fuel applications,… (more)

Subjects/Keywords: Zirconium; Hydride; Zircaloy; spent nuclear fuel; Recycle; milling

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APA (6th Edition):

Kelley, R. D. (2011). Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8487

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kelley, Randy Dean. “Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process.” 2011. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8487.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kelley, Randy Dean. “Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process.” 2011. Web. 16 Feb 2019.

Vancouver:

Kelley RD. Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process. [Internet] [Thesis]. Texas A&M University; 2011. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8487.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kelley RD. Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process. [Thesis]. Texas A&M University; 2011. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-08-8487

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

29. Helmreich, Grant. Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications.

Degree: 2012, Texas A&M University

 The sintering behavior of uranium and uranium-zirconium alloys in the alpha phase were characterized in this research. Metal uranium powder was produced from pieces of… (more)

Subjects/Keywords: Uranium; alpha-phase; sintering; zirconium; nuclear fuel cycle

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APA (6th Edition):

Helmreich, G. (2012). Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8981

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Helmreich, Grant. “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8981.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Helmreich, Grant. “Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications.” 2012. Web. 16 Feb 2019.

Vancouver:

Helmreich G. Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8981.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Helmreich G. Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8981

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

30. Humrickhouse, Carissa Joy. Characterization of Thermal Properties of Depleted Uranium Metal Microspheres.

Degree: 2012, Texas A&M University

 Nuclear fuel comes in many forms; oxide fuel is the most commonly used in current reactor systems while metal fuel is a promising fuel type… (more)

Subjects/Keywords: Nuclear fuel; uranium metal; microspheres; sphere-pac; Travelling Wave Reactor; Laser Flash Analysis; Thermal diffusivity; Thermal conductivity

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Humrickhouse, C. J. (2012). Characterization of Thermal Properties of Depleted Uranium Metal Microspheres. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10979

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Humrickhouse, Carissa Joy. “Characterization of Thermal Properties of Depleted Uranium Metal Microspheres.” 2012. Thesis, Texas A&M University. Accessed February 16, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10979.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Humrickhouse, Carissa Joy. “Characterization of Thermal Properties of Depleted Uranium Metal Microspheres.” 2012. Web. 16 Feb 2019.

Vancouver:

Humrickhouse CJ. Characterization of Thermal Properties of Depleted Uranium Metal Microspheres. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Feb 16]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10979.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Humrickhouse CJ. Characterization of Thermal Properties of Depleted Uranium Metal Microspheres. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10979

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

[1] [2]

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