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You searched for subject:(Nuclear Fuel). Showing records 1 – 30 of 456 total matches.

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University of California – Berkeley

1. Terrani, Kurt Amir. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors.

Degree: Nuclear Engineering, 2010, University of California – Berkeley

 This dissertation intends to examine basic materials properties, identify optimized fabrication techniques, model behavior under relevant environments, and experimentally quantify kinetic phenomena associated with hydride… (more)

Subjects/Keywords: Nuclear Engineering; Hydride Fuel; Nuclear Fuel

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APA (6th Edition):

Terrani, K. A. (2010). Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/48d78064

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):

Terrani, Kurt Amir. “Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors.” 2010. Thesis, University of California – Berkeley. Accessed May 26, 2019. http://www.escholarship.org/uc/item/48d78064.

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

MLA Handbook (7th Edition):

Terrani, Kurt Amir. “Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors.” 2010. Web. 26 May 2019.

Vancouver:

Terrani KA. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2019 May 26]. Available from: http://www.escholarship.org/uc/item/48d78064.

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

Council of Science Editors:

Terrani KA. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors. [Thesis]. University of California – Berkeley; 2010. Available from: http://www.escholarship.org/uc/item/48d78064

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


University of Manchester

2. Tucker, Kate Louise. Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems.

Degree: 2015, University of Manchester

 Understanding the behaviour of heavy metals involved in the nuclear fuel cycle is of paramount importance to the reprocessing and storage of spent nuclear fuel.… (more)

Subjects/Keywords: Nuclear fuel reprocessing

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APA (6th Edition):

Tucker, K. L. (2015). Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686

Chicago Manual of Style (16th Edition):

Tucker, Kate Louise. “Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems.” 2015. Doctoral Dissertation, University of Manchester. Accessed May 26, 2019. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686.

MLA Handbook (7th Edition):

Tucker, Kate Louise. “Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems.” 2015. Web. 26 May 2019.

Vancouver:

Tucker KL. Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems. [Internet] [Doctoral dissertation]. University of Manchester; 2015. [cited 2019 May 26]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686.

Council of Science Editors:

Tucker KL. Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems. [Doctoral Dissertation]. University of Manchester; 2015. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686


University of New Mexico

3. Edelmann, Paul. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel.

Degree: Nuclear Engineering, 2013, University of New Mexico

 There have been numerous attempts to model fast reactor fuel behavior in the last 40 years. The US currently does not have a fully reliable… (more)

Subjects/Keywords: nuclear; fuel; diffusion

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APA (6th Edition):

Edelmann, P. (2013). Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/23107

Chicago Manual of Style (16th Edition):

Edelmann, Paul. “Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel.” 2013. Doctoral Dissertation, University of New Mexico. Accessed May 26, 2019. http://hdl.handle.net/1928/23107.

MLA Handbook (7th Edition):

Edelmann, Paul. “Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel.” 2013. Web. 26 May 2019.

Vancouver:

Edelmann P. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel. [Internet] [Doctoral dissertation]. University of New Mexico; 2013. [cited 2019 May 26]. Available from: http://hdl.handle.net/1928/23107.

Council of Science Editors:

Edelmann P. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel. [Doctoral Dissertation]. University of New Mexico; 2013. Available from: http://hdl.handle.net/1928/23107


University of Texas – Austin

4. -3703-6555. Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling.

Degree: Mechanical Engineering, 2015, University of Texas – Austin

 The large number of reactor designs and concepts in existence open up a vast array of nuclear fuel cycle strategies. u. These different reactor types… (more)

Subjects/Keywords: Nuclear fuel cycle; Reactor modeling; Fuel blending

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APA (6th Edition):

-3703-6555. (2015). Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/45763

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

Chicago Manual of Style (16th Edition):

-3703-6555. “Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling.” 2015. Thesis, University of Texas – Austin. Accessed May 26, 2019. http://hdl.handle.net/2152/45763.

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

MLA Handbook (7th Edition):

-3703-6555. “Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling.” 2015. Web. 26 May 2019.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Vancouver:

-3703-6555. Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling. [Internet] [Thesis]. University of Texas – Austin; 2015. [cited 2019 May 26]. Available from: http://hdl.handle.net/2152/45763.

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

Council of Science Editors:

-3703-6555. Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling. [Thesis]. University of Texas – Austin; 2015. Available from: http://hdl.handle.net/2152/45763

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


University of Manchester

5. Tucker, Kate Louise. Heavy metal extraction using advanced liquid-liquid style partitioning systems.

Degree: PhD, 2015, University of Manchester

 Understanding the behaviour of heavy metals involved in the nuclear fuel cycle is of paramount importance to the reprocessing and storage of spent nuclear fuel.… (more)

Subjects/Keywords: 553.4; Nuclear fuel reprocessing

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

APA (6th Edition):

Tucker, K. L. (2015). Heavy metal extraction using advanced liquid-liquid style partitioning systems. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/heavy-metal-extraction-using-advanced-liquid – liquid-style-partitioning-systems(6a238cb4-94cf-4fa8-bffe-d1a1b70adaa6).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.677739

Chicago Manual of Style (16th Edition):

Tucker, Kate Louise. “Heavy metal extraction using advanced liquid-liquid style partitioning systems.” 2015. Doctoral Dissertation, University of Manchester. Accessed May 26, 2019. https://www.research.manchester.ac.uk/portal/en/theses/heavy-metal-extraction-using-advanced-liquid – liquid-style-partitioning-systems(6a238cb4-94cf-4fa8-bffe-d1a1b70adaa6).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.677739.

MLA Handbook (7th Edition):

Tucker, Kate Louise. “Heavy metal extraction using advanced liquid-liquid style partitioning systems.” 2015. Web. 26 May 2019.

Vancouver:

Tucker KL. Heavy metal extraction using advanced liquid-liquid style partitioning systems. [Internet] [Doctoral dissertation]. University of Manchester; 2015. [cited 2019 May 26]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/heavy-metal-extraction-using-advanced-liquid – liquid-style-partitioning-systems(6a238cb4-94cf-4fa8-bffe-d1a1b70adaa6).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.677739.

Council of Science Editors:

Tucker KL. Heavy metal extraction using advanced liquid-liquid style partitioning systems. [Doctoral Dissertation]. University of Manchester; 2015. Available from: https://www.research.manchester.ac.uk/portal/en/theses/heavy-metal-extraction-using-advanced-liquid – liquid-style-partitioning-systems(6a238cb4-94cf-4fa8-bffe-d1a1b70adaa6).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.677739


Virginia Tech

6. Faierson, Eric J. Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite.

Degree: PhD, Materials Science and Engineering, 2011, Virginia Tech

 Ceramic and refractory metal foams have a potential for use in extreme environments, such as in fuel elements within nuclear reactors both in space and… (more)

Subjects/Keywords: foam; composite; neutron; nuclear fuel

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APA (6th Edition):

Faierson, E. J. (2011). Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/28688

Chicago Manual of Style (16th Edition):

Faierson, Eric J. “Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite.” 2011. Doctoral Dissertation, Virginia Tech. Accessed May 26, 2019. http://hdl.handle.net/10919/28688.

MLA Handbook (7th Edition):

Faierson, Eric J. “Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite.” 2011. Web. 26 May 2019.

Vancouver:

Faierson EJ. Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite. [Internet] [Doctoral dissertation]. Virginia Tech; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/10919/28688.

Council of Science Editors:

Faierson EJ. Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite. [Doctoral Dissertation]. Virginia Tech; 2011. Available from: http://hdl.handle.net/10919/28688


Uppsala University

7. Lundkvist, Niklas. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.

Degree: Applied Nuclear Physics, 2010, Uppsala University

This report is concerned with the question whether Accelerator mass spectrometry (AMS) is asuitable technique for measuring actinide inventory in spent nuclear fuel, and… (more)

Subjects/Keywords: AMS; actinides; spent; nuclear; fuel

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APA (6th Edition):

Lundkvist, N. (2010). AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011

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):

Lundkvist, Niklas. “AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.” 2010. Thesis, Uppsala University. Accessed May 26, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011.

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

MLA Handbook (7th Edition):

Lundkvist, Niklas. “AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.” 2010. Web. 26 May 2019.

Vancouver:

Lundkvist N. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 May 26]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011.

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

Council of Science Editors:

Lundkvist N. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011

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


University of Texas – Austin

8. Bagdatlioglu, Cem. A hybrid global surrogate modeling software for nuclear reactor cross section estimation.

Degree: Mechanical Engineering, 2017, University of Texas – Austin

Nuclear fuel cycle (NFC) simulators track the amount and composition of materials as they move through facilities such as mines, fuel fabrication plants, and nuclear(more)

Subjects/Keywords: Nuclear; Fuel cycle; Surrogate model

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APA (6th Edition):

Bagdatlioglu, C. (2017). A hybrid global surrogate modeling software for nuclear reactor cross section estimation. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/63039

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):

Bagdatlioglu, Cem. “A hybrid global surrogate modeling software for nuclear reactor cross section estimation.” 2017. Thesis, University of Texas – Austin. Accessed May 26, 2019. http://hdl.handle.net/2152/63039.

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

MLA Handbook (7th Edition):

Bagdatlioglu, Cem. “A hybrid global surrogate modeling software for nuclear reactor cross section estimation.” 2017. Web. 26 May 2019.

Vancouver:

Bagdatlioglu C. A hybrid global surrogate modeling software for nuclear reactor cross section estimation. [Internet] [Thesis]. University of Texas – Austin; 2017. [cited 2019 May 26]. Available from: http://hdl.handle.net/2152/63039.

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

Council of Science Editors:

Bagdatlioglu C. A hybrid global surrogate modeling software for nuclear reactor cross section estimation. [Thesis]. University of Texas – Austin; 2017. Available from: http://hdl.handle.net/2152/63039

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


University of Illinois – Urbana-Champaign

9. Lartonoix, David. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.

Degree: MS, 5183, 2012, University of Illinois – Urbana-Champaign

 While nuclear reactors in the United States have produced economy-driving power for several decades, they have also left behind a significant amount of spent nuclear(more)

Subjects/Keywords: spent nuclear fuel; radioisotope inventory

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APA (6th Edition):

Lartonoix, D. (2012). Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/31990

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):

Lartonoix, David. “Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.” 2012. Thesis, University of Illinois – Urbana-Champaign. Accessed May 26, 2019. http://hdl.handle.net/2142/31990.

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

MLA Handbook (7th Edition):

Lartonoix, David. “Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.” 2012. Web. 26 May 2019.

Vancouver:

Lartonoix D. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/2142/31990.

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

Council of Science Editors:

Lartonoix D. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. [Thesis]. University of Illinois – Urbana-Champaign; 2012. Available from: http://hdl.handle.net/2142/31990

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


Virginia Commonwealth University

10. Britt, Taylor C. Innovative Fuel Design to Improve Proliferation Management.

Degree: MS, Mechanical and Nuclear Engineering, 2018, Virginia Commonwealth University

  This research uses an existing innovative fuel design (IFD) that has intrinsic safety features and enhanced economics over the current uranium dioxide (UO2) light… (more)

Subjects/Keywords: Nuclear; Nonproliferation; Fuel; Plutonium; MCNP; Nuclear Engineering

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APA (6th Edition):

Britt, T. C. (2018). Innovative Fuel Design to Improve Proliferation Management. (Thesis). Virginia Commonwealth University. Retrieved from https://scholarscompass.vcu.edu/etd/5690

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):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Thesis, Virginia Commonwealth University. Accessed May 26, 2019. https://scholarscompass.vcu.edu/etd/5690.

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

MLA Handbook (7th Edition):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Web. 26 May 2019.

Vancouver:

Britt TC. Innovative Fuel Design to Improve Proliferation Management. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 May 26]. Available from: https://scholarscompass.vcu.edu/etd/5690.

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

Council of Science Editors:

Britt TC. Innovative Fuel Design to Improve Proliferation Management. [Thesis]. Virginia Commonwealth University; 2018. Available from: https://scholarscompass.vcu.edu/etd/5690

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


Virginia Commonwealth University

11. Britton, Kyle A. Neutronics Studies on the NIST Reactor Using the GA LEU fuel.

Degree: MS, Mechanical and Nuclear Engineering, 2018, Virginia Commonwealth University

  The National Bureau of Standards Reactor (NBSR) located on the National Institute of Standards and Technology (NIST) Gaithersburg campus, is currently underway of fuel(more)

Subjects/Keywords: Neutronics; NBSR; TRIGA fuel; LEU fuel; Research Reactor; Nuclear; Nuclear Engineering

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APA (6th Edition):

Britton, K. A. (2018). Neutronics Studies on the NIST Reactor Using the GA LEU fuel. (Thesis). Virginia Commonwealth University. Retrieved from https://scholarscompass.vcu.edu/etd/5702

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):

Britton, Kyle A. “Neutronics Studies on the NIST Reactor Using the GA LEU fuel.” 2018. Thesis, Virginia Commonwealth University. Accessed May 26, 2019. https://scholarscompass.vcu.edu/etd/5702.

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

MLA Handbook (7th Edition):

Britton, Kyle A. “Neutronics Studies on the NIST Reactor Using the GA LEU fuel.” 2018. Web. 26 May 2019.

Vancouver:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 May 26]. Available from: https://scholarscompass.vcu.edu/etd/5702.

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

Council of Science Editors:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Thesis]. Virginia Commonwealth University; 2018. Available from: https://scholarscompass.vcu.edu/etd/5702

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


University of Illinois – Urbana-Champaign

12. Taylor, J'Tia P. An analysis of international nuclear fuel supply options.

Degree: PhD, 0139, 2010, University of Illinois – Urbana-Champaign

 As the global demand for energy grows, many nations are considering developing or increasing nuclear capacity as a viable, long-term power source. To assess the… (more)

Subjects/Keywords: Nuclear fuel cycle; fuel supply; energy security; fuel supply chain

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APA (6th Edition):

Taylor, J. P. (2010). An analysis of international nuclear fuel supply options. (Doctoral Dissertation). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/16123

Chicago Manual of Style (16th Edition):

Taylor, J'Tia P. “An analysis of international nuclear fuel supply options.” 2010. Doctoral Dissertation, University of Illinois – Urbana-Champaign. Accessed May 26, 2019. http://hdl.handle.net/2142/16123.

MLA Handbook (7th Edition):

Taylor, J'Tia P. “An analysis of international nuclear fuel supply options.” 2010. Web. 26 May 2019.

Vancouver:

Taylor JP. An analysis of international nuclear fuel supply options. [Internet] [Doctoral dissertation]. University of Illinois – Urbana-Champaign; 2010. [cited 2019 May 26]. Available from: http://hdl.handle.net/2142/16123.

Council of Science Editors:

Taylor JP. An analysis of international nuclear fuel supply options. [Doctoral Dissertation]. University of Illinois – Urbana-Champaign; 2010. Available from: http://hdl.handle.net/2142/16123


Texas A&M University

13. 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 May 26, 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. 26 May 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 May 26]. 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


The Ohio State University

14. Yee, Shannon K. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.

Degree: MS, Nuclear Engineering, 2008, The Ohio State University

 Policy decisions regarding the direction of nuclear power utilize sophisticated fuel cycle models. Both static and dynamic models are used to determine how a proposed… (more)

Subjects/Keywords: Engineering; Mechanical Engineering; Nuclear Chemistry; Nuclear Physics; Physics; fuel cycle; spent nuclear fuel; nuclear fuel recycling; transmutation

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APA (6th Edition):

Yee, S. K. (2008). Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425

Chicago Manual of Style (16th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Masters Thesis, The Ohio State University. Accessed May 26, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

MLA Handbook (7th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Web. 26 May 2019.

Vancouver:

Yee SK. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 May 26]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

Council of Science Editors:

Yee SK. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. [Masters Thesis]. The Ohio State University; 2008. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425

15. Kelly Cristina Martins Faêda. Caracterização do combustível para reatores nucleares produtores de hidrogênio.

Degree: Master, 2011, Centro de Desenvolvimento da Tecnologia Nuclear

Reatores nucleares de 4 geração do tipo HTGR (reatores de alta temperatura refrigerados a gás) apresentam vantagens em relação a um reator a água pressurizada,… (more)

Subjects/Keywords: COMBUSTIVEL NUCLEAR; Reator Nuclear Combustível Nuclear Analises química; Nuclear fuel Nuclear reactor Chemical analysis

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

APA (6th Edition):

Faêda, K. C. M. (2011). Caracterização do combustível para reatores nucleares produtores de hidrogênio. (Masters Thesis). Centro de Desenvolvimento da Tecnologia Nuclear. Retrieved from http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;

Chicago Manual of Style (16th Edition):

Faêda, Kelly Cristina Martins. “Caracterização do combustível para reatores nucleares produtores de hidrogênio.” 2011. Masters Thesis, Centro de Desenvolvimento da Tecnologia Nuclear. Accessed May 26, 2019. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;.

MLA Handbook (7th Edition):

Faêda, Kelly Cristina Martins. “Caracterização do combustível para reatores nucleares produtores de hidrogênio.” 2011. Web. 26 May 2019.

Vancouver:

Faêda KCM. Caracterização do combustível para reatores nucleares produtores de hidrogênio. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2011. [cited 2019 May 26]. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;.

Council of Science Editors:

Faêda KCM. Caracterização do combustível para reatores nucleares produtores de hidrogênio. [Masters Thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2011. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;


Texas A&M University

16. Totemeier, Aaron Robert. Helium Ion Implantation in Zirconium: Bubble Formation & Growth.

Degree: 2015, Texas A&M University

 To evaluate the behavior of inert helium gas bubbles in zirconium three variants of the metal were implanted with 140 keV helium ions to a… (more)

Subjects/Keywords: Nuclear; Zirconium, Helium Bubbles; Ion Implantation; Nuclear Fuel; Nuclear Waste

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APA (6th Edition):

Totemeier, A. R. (2015). Helium Ion Implantation in Zirconium: Bubble Formation & Growth. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156473

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):

Totemeier, Aaron Robert. “Helium Ion Implantation in Zirconium: Bubble Formation & Growth.” 2015. Thesis, Texas A&M University. Accessed May 26, 2019. http://hdl.handle.net/1969.1/156473.

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

MLA Handbook (7th Edition):

Totemeier, Aaron Robert. “Helium Ion Implantation in Zirconium: Bubble Formation & Growth.” 2015. Web. 26 May 2019.

Vancouver:

Totemeier AR. Helium Ion Implantation in Zirconium: Bubble Formation & Growth. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 May 26]. Available from: http://hdl.handle.net/1969.1/156473.

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

Council of Science Editors:

Totemeier AR. Helium Ion Implantation in Zirconium: Bubble Formation & Growth. [Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/156473

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


EPFL

17. Brankov, Vladimir Vladimirov. Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor.

Degree: 2017, EPFL

 Recent LOCA tests with high burnup fuel at the OECD Halden Reactor Project and at Studsvik demonstrated the susceptibility of the fuel to fragment to… (more)

Subjects/Keywords: FFRD Modelling; nuclear power; nuclear fuel; high burnup; fuel fragmentation; fuel relocation; fuel dispersal; LOCA; Halden LOCA tests; FALCON

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APA (6th Edition):

Brankov, V. V. (2017). Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/231951

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):

Brankov, Vladimir Vladimirov. “Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor.” 2017. Thesis, EPFL. Accessed May 26, 2019. http://infoscience.epfl.ch/record/231951.

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

MLA Handbook (7th Edition):

Brankov, Vladimir Vladimirov. “Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor.” 2017. Web. 26 May 2019.

Vancouver:

Brankov VV. Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor. [Internet] [Thesis]. EPFL; 2017. [cited 2019 May 26]. Available from: http://infoscience.epfl.ch/record/231951.

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

Council of Science Editors:

Brankov VV. Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor. [Thesis]. EPFL; 2017. Available from: http://infoscience.epfl.ch/record/231951

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


University of Tennessee – Knoxville

18. Petersen, Gordon Matthew. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.

Degree: 2016, University of Tennessee – Knoxville

 Commercial nuclear power plants produce long-lasting nuclear waste, primarily in the form of spent nuclear fuel (SNF) assemblies. Spent fuel pools (SFP) and canisters or… (more)

Subjects/Keywords: Optimization; Spent Nuclear Fuel; Allocation Strategy; Fuel Removal; Used Nuclear Fuel; Tractable Validation Model; Nuclear Engineering

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APA (6th Edition):

Petersen, G. M. (2016). Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/4156

Chicago Manual of Style (16th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed May 26, 2019. https://trace.tennessee.edu/utk_graddiss/4156.

MLA Handbook (7th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Web. 26 May 2019.

Vancouver:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2019 May 26]. Available from: https://trace.tennessee.edu/utk_graddiss/4156.

Council of Science Editors:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_graddiss/4156


McMaster University

19. Friedlander, Yonni. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.

Degree: MASc, 2011, McMaster University

A study was conducted to scope the relative merits of various thorium fuel cycles in CANDU reactors. It was determined that, due to the… (more)

Subjects/Keywords: Nuclear; Advanced Fuel Cycles; Thorium; CANDU; Nuclear resources; Nuclear Engineering; Nuclear Engineering

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

APA (6th Edition):

Friedlander, Y. (2011). A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11283

Chicago Manual of Style (16th Edition):

Friedlander, Yonni. “A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.” 2011. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/11283.

MLA Handbook (7th Edition):

Friedlander, Yonni. “A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.” 2011. Web. 26 May 2019.

Vancouver:

Friedlander Y. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/11283.

Council of Science Editors:

Friedlander Y. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11283


University of Ontario Institute of Technology

20. Peiman, Wargha. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).

Degree: 2017, University of Ontario Institute of Technology

 A group of countries has initiated an international collaboration to develop a next generation (i.e., Generation IV) of nuclear reactors. Chosen as one of the… (more)

Subjects/Keywords: SCWR; Thermalhydraulics; Neutronics; Generation IV; Nuclear fuel

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APA (6th Edition):

Peiman, W. (2017). Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/827

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):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/827.

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

MLA Handbook (7th Edition):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Web. 26 May 2019.

Vancouver:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Internet] [Thesis]. University of Ontario Institute of Technology; 2017. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/827.

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

Council of Science Editors:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Thesis]. University of Ontario Institute of Technology; 2017. Available from: http://hdl.handle.net/10155/827

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


Texas A&M University

21. 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 May 26, 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. 26 May 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 May 26]. 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


University of Pretoria

22. Hlatshwayo, Thulani Thokozani. Diffusion of silver in 6H-SiC.

Degree: Physics, 2011, University of Pretoria

 SiC is used as the main diffusion barrier in the fuel spheres of the pebble bed modular reactor (PBMR). The PBMR is a modern high… (more)

Subjects/Keywords: Nuclear reactor; Fuel spheres; Diffusion barrier; UCTD

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APA (6th Edition):

Hlatshwayo, T. T. (2011). Diffusion of silver in 6H-SiC. (Doctoral Dissertation). University of Pretoria. Retrieved from http://hdl.handle.net/2263/25616

Chicago Manual of Style (16th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC.” 2011. Doctoral Dissertation, University of Pretoria. Accessed May 26, 2019. http://hdl.handle.net/2263/25616.

MLA Handbook (7th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC.” 2011. Web. 26 May 2019.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC. [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/2263/25616.

Council of Science Editors:

Hlatshwayo TT. Diffusion of silver in 6H-SiC. [Doctoral Dissertation]. University of Pretoria; 2011. Available from: http://hdl.handle.net/2263/25616


University of Pretoria

23. Hlatshwayo, Thulani Thokozani. Diffusion of silver in 6H-SiC .

Degree: 2011, University of Pretoria

 SiC is used as the main diffusion barrier in the fuel spheres of the pebble bed modular reactor (PBMR). The PBMR is a modern high… (more)

Subjects/Keywords: Nuclear reactor; Fuel spheres; Diffusion barrier; UCTD

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

APA (6th Edition):

Hlatshwayo, T. T. (2011). Diffusion of silver in 6H-SiC . (Doctoral Dissertation). University of Pretoria. Retrieved from http://upetd.up.ac.za/thesis/available/etd-06182011-165556/

Chicago Manual of Style (16th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC .” 2011. Doctoral Dissertation, University of Pretoria. Accessed May 26, 2019. http://upetd.up.ac.za/thesis/available/etd-06182011-165556/.

MLA Handbook (7th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC .” 2011. Web. 26 May 2019.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC . [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2019 May 26]. Available from: http://upetd.up.ac.za/thesis/available/etd-06182011-165556/.

Council of Science Editors:

Hlatshwayo TT. Diffusion of silver in 6H-SiC . [Doctoral Dissertation]. University of Pretoria; 2011. Available from: http://upetd.up.ac.za/thesis/available/etd-06182011-165556/


Oregon State University

24. Vincent, Andrew M. Fuel-cladding mechanical interaction in simulated sphere pac fuel.

Degree: MS, Nuclear Engineering, 1981, Oregon State University

 A study has been made to investigate the fuel-cladding mechanical interaction (FCMI) in sphere pac fuels. An FCMI simulation has been constructed using the JVG… (more)

Subjects/Keywords: Nuclear fuel claddings

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APA (6th Edition):

Vincent, A. M. (1981). Fuel-cladding mechanical interaction in simulated sphere pac fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41696

Chicago Manual of Style (16th Edition):

Vincent, Andrew M. “Fuel-cladding mechanical interaction in simulated sphere pac fuel.” 1981. Masters Thesis, Oregon State University. Accessed May 26, 2019. http://hdl.handle.net/1957/41696.

MLA Handbook (7th Edition):

Vincent, Andrew M. “Fuel-cladding mechanical interaction in simulated sphere pac fuel.” 1981. Web. 26 May 2019.

Vancouver:

Vincent AM. Fuel-cladding mechanical interaction in simulated sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 May 26]. Available from: http://hdl.handle.net/1957/41696.

Council of Science Editors:

Vincent AM. Fuel-cladding mechanical interaction in simulated sphere pac fuel. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/41696


University of Saskatchewan

25. Oladimeji, Dotun J 1989-. Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup.

Degree: 2017, University of Saskatchewan

Nuclear fuel performance during reactor operation has been studied using both atomic scale simulation and experimental procedure in order to investigate how nuclear fission process… (more)

Subjects/Keywords: Nuclear Fuel; Molecular Dynamics; Thermal conductivity

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APA (6th Edition):

Oladimeji, D. J. 1. (2017). Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup. (Thesis). University of Saskatchewan. Retrieved from http://hdl.handle.net/10388/8024

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):

Oladimeji, Dotun J 1989-. “Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup.” 2017. Thesis, University of Saskatchewan. Accessed May 26, 2019. http://hdl.handle.net/10388/8024.

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

MLA Handbook (7th Edition):

Oladimeji, Dotun J 1989-. “Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup.” 2017. Web. 26 May 2019.

Vancouver:

Oladimeji DJ1. Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup. [Internet] [Thesis]. University of Saskatchewan; 2017. [cited 2019 May 26]. Available from: http://hdl.handle.net/10388/8024.

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

Council of Science Editors:

Oladimeji DJ1. Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup. [Thesis]. University of Saskatchewan; 2017. Available from: http://hdl.handle.net/10388/8024

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


Oregon State University

26. Clark, R. G. (Robert Gilder), 1917-2005. Monitoring surface temperature of irradiated fuel elements.

Degree: MS, Electrical Engineering, 1963, Oregon State University

Subjects/Keywords: Nuclear fuel elements

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APA (6th Edition):

Clark, R. G. (Robert Gilder), 1. (1963). Monitoring surface temperature of irradiated fuel elements. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/48787

Chicago Manual of Style (16th Edition):

Clark, R. G. (Robert Gilder), 1917-2005. “Monitoring surface temperature of irradiated fuel elements.” 1963. Masters Thesis, Oregon State University. Accessed May 26, 2019. http://hdl.handle.net/1957/48787.

MLA Handbook (7th Edition):

Clark, R. G. (Robert Gilder), 1917-2005. “Monitoring surface temperature of irradiated fuel elements.” 1963. Web. 26 May 2019.

Vancouver:

Clark, R. G. (Robert Gilder) 1. Monitoring surface temperature of irradiated fuel elements. [Internet] [Masters thesis]. Oregon State University; 1963. [cited 2019 May 26]. Available from: http://hdl.handle.net/1957/48787.

Council of Science Editors:

Clark, R. G. (Robert Gilder) 1. Monitoring surface temperature of irradiated fuel elements. [Masters Thesis]. Oregon State University; 1963. Available from: http://hdl.handle.net/1957/48787


Oregon State University

27. Latimer, Griffen D. Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF.

Degree: MS, Nuclear Engineering, 2016, Oregon State University

 Current research on the topic of advanced reactor fuel types include the use of ultrahigh density Uranium-Molybdenum fuels, towards their use in high-performance research reactors.… (more)

Subjects/Keywords: Flow Induced Vibration; Nuclear fuel elements  – Testing

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APA (6th Edition):

Latimer, G. D. (2016). Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/60099

Chicago Manual of Style (16th Edition):

Latimer, Griffen D. “Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF.” 2016. Masters Thesis, Oregon State University. Accessed May 26, 2019. http://hdl.handle.net/1957/60099.

MLA Handbook (7th Edition):

Latimer, Griffen D. “Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF.” 2016. Web. 26 May 2019.

Vancouver:

Latimer GD. Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 May 26]. Available from: http://hdl.handle.net/1957/60099.

Council of Science Editors:

Latimer GD. Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/60099


University of Tennessee – Knoxville

28. Littell, Jennifer Lynn. Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options.

Degree: MS, Nuclear Engineering, 2016, University of Tennessee – Knoxville

  The Nuclear Fuel Cycle Evaluation and Screening Study was chartered by the DOE in order to weigh the relative benefits and challenges of potential… (more)

Subjects/Keywords: nuclear fuel cycle; ORIGEN; Cyclus; ORION

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APA (6th Edition):

Littell, J. L. (2016). Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/3783

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):

Littell, Jennifer Lynn. “Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options.” 2016. Thesis, University of Tennessee – Knoxville. Accessed May 26, 2019. https://trace.tennessee.edu/utk_gradthes/3783.

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

MLA Handbook (7th Edition):

Littell, Jennifer Lynn. “Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options.” 2016. Web. 26 May 2019.

Vancouver:

Littell JL. Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options. [Internet] [Thesis]. University of Tennessee – Knoxville; 2016. [cited 2019 May 26]. Available from: https://trace.tennessee.edu/utk_gradthes/3783.

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

Council of Science Editors:

Littell JL. Development and Application of Nuclear Fuel Cycle Simulators for Evaluating Potential Fuel Cycle Options. [Thesis]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_gradthes/3783

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

29. Vieira, Edeval. Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI.

Degree: Mestrado, Tecnologia Nuclear - Materiais, 2011, University of São Paulo

O Instituto de Pesquisas Energéticas e Nucleares IPEN-CNEN/SP atualmente produz rotineiramente o combustível nuclear necessário para a operação de seu reator de pesquisas IEA-R1. Esse… (more)

Subjects/Keywords: combustível nuclear; deformação; deformation; dispersão; dispersion; fuel plates; nuclear fuel; placas combustíveis

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

APA (6th Edition):

Vieira, E. (2011). Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85134/tde-02032012-133617/ ;

Chicago Manual of Style (16th Edition):

Vieira, Edeval. “Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI.” 2011. Masters Thesis, University of São Paulo. Accessed May 26, 2019. http://www.teses.usp.br/teses/disponiveis/85/85134/tde-02032012-133617/ ;.

MLA Handbook (7th Edition):

Vieira, Edeval. “Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI.” 2011. Web. 26 May 2019.

Vancouver:

Vieira E. Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI. [Internet] [Masters thesis]. University of São Paulo; 2011. [cited 2019 May 26]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85134/tde-02032012-133617/ ;.

Council of Science Editors:

Vieira E. Estudo paramétrico da deformação de placas combutíveis com núcleos de dispersão de U3Si2-AI. [Masters Thesis]. University of São Paulo; 2011. Available from: http://www.teses.usp.br/teses/disponiveis/85/85134/tde-02032012-133617/ ;


Brno University of Technology

30. Ježek, Martin. Palivový cyklus jaderné elektrárny Temelín .

Degree: 2012, Brno University of Technology

 Tato bakalářská práce se zabývá střední částí palivového cyklu jaderné elektrárny Temelín. Popisuje obecně celý palivový cyklus, od těžby uranu až po trvalé uložení vyhořelého… (more)

Subjects/Keywords: palivový cyklus; jaderné palivo; Temelín; VVER; Nuclear fuel cycle; nuclear fuel; Temelin; VVER

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

APA (6th Edition):

Ježek, M. (2012). Palivový cyklus jaderné elektrárny Temelín . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/11531

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):

Ježek, Martin. “Palivový cyklus jaderné elektrárny Temelín .” 2012. Thesis, Brno University of Technology. Accessed May 26, 2019. http://hdl.handle.net/11012/11531.

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

MLA Handbook (7th Edition):

Ježek, Martin. “Palivový cyklus jaderné elektrárny Temelín .” 2012. Web. 26 May 2019.

Vancouver:

Ježek M. Palivový cyklus jaderné elektrárny Temelín . [Internet] [Thesis]. Brno University of Technology; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/11012/11531.

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

Council of Science Editors:

Ježek M. Palivový cyklus jaderné elektrárny Temelín . [Thesis]. Brno University of Technology; 2012. Available from: http://hdl.handle.net/11012/11531

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

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