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You searched for subject:(nuclear fuel). Showing records 1 – 30 of 472 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Terrani KA. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2021 Mar 03]. 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 New Mexico

2. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Edelmann P. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel. [Internet] [Doctoral dissertation]. University of New Mexico; 2013. [cited 2021 Mar 03]. 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 Manchester

3. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Tucker KL. Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems. [Internet] [Doctoral dissertation]. University of Manchester; 2015. [cited 2021 Mar 03]. 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 Texas – Austin

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

Degree: PhD, 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. (Doctoral Dissertation). 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

Chicago Manual of Style (16th Edition):

-3703-6555. “Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling.” 2015. Doctoral Dissertation, University of Texas – Austin. Accessed March 03, 2021. http://hdl.handle.net/2152/45763.

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

MLA Handbook (7th Edition):

-3703-6555. “Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling.” 2015. Web. 03 Mar 2021.

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] [Doctoral dissertation]. University of Texas – Austin; 2015. [cited 2021 Mar 03]. 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

Council of Science Editors:

-3703-6555. Novel methods for generalizing nuclear fuel cycle design, and fuel burnup modeling. [Doctoral Dissertation]. 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


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 (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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Tucker KL. Heavy metal extraction using advanced liquid-liquid style partitioning systems. [Internet] [Doctoral dissertation]. University of Manchester; 2015. [cited 2021 Mar 03]. 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


University of Illinois – Urbana-Champaign

6. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Lartonoix D. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2012. [cited 2021 Mar 03]. 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 Tech

7. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Faierson EJ. Structure-Property Relationships of Tantalum Carbide Foams and Synthesis of an Interpenetrating Phase Composite. [Internet] [Doctoral dissertation]. Virginia Tech; 2011. [cited 2021 Mar 03]. 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


University of South Carolina

8. Shalloo, Matthew. Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel.

Degree: Degree ofMSin Nuclear Engineering, Nuclear Engineering, 2019, University of South Carolina

  Research reactors such as the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR) employ aluminum-clad fuel elements made up of many… (more)

Subjects/Keywords: Nuclear Engineering; nuclear fuel; fuel; Aluminum Clad; Oxyhydroxides

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APA (6th Edition):

Shalloo, M. (2019). Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel. (Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/5509

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):

Shalloo, Matthew. “Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel.” 2019. Thesis, University of South Carolina. Accessed March 03, 2021. https://scholarcommons.sc.edu/etd/5509.

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

MLA Handbook (7th Edition):

Shalloo, Matthew. “Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel.” 2019. Web. 03 Mar 2021.

Vancouver:

Shalloo M. Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel. [Internet] [Thesis]. University of South Carolina; 2019. [cited 2021 Mar 03]. Available from: https://scholarcommons.sc.edu/etd/5509.

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

Council of Science Editors:

Shalloo M. Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel. [Thesis]. University of South Carolina; 2019. Available from: https://scholarcommons.sc.edu/etd/5509

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


Texas A&M University

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

Degree: MS, Nuclear Engineering, 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. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156356

Chicago Manual of Style (16th Edition):

Smith, Joshua 1987-. “Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses.” 2012. Masters Thesis, Texas A&M University. Accessed March 03, 2021. http://hdl.handle.net/1969.1/156356.

MLA Handbook (7th Edition):

Smith, Joshua 1987-. “Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses.” 2012. Web. 03 Mar 2021.

Vancouver:

Smith J1. Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 03]. Available from: http://hdl.handle.net/1969.1/156356.

Council of Science Editors:

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

10. 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 (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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Faêda KCM. Caracterização do combustível para reatores nucleares produtores de hidrogênio. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2011. [cited 2021 Mar 03]. 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

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

Degree: PhD, Nuclear Engineering, 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. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156473

Chicago Manual of Style (16th Edition):

Totemeier, Aaron Robert. “Helium Ion Implantation in Zirconium: Bubble Formation & Growth.” 2015. Doctoral Dissertation, Texas A&M University. Accessed March 03, 2021. http://hdl.handle.net/1969.1/156473.

MLA Handbook (7th Edition):

Totemeier, Aaron Robert. “Helium Ion Implantation in Zirconium: Bubble Formation & Growth.” 2015. Web. 03 Mar 2021.

Vancouver:

Totemeier AR. Helium Ion Implantation in Zirconium: Bubble Formation & Growth. [Internet] [Doctoral dissertation]. Texas A&M University; 2015. [cited 2021 Mar 03]. Available from: http://hdl.handle.net/1969.1/156473.

Council of Science Editors:

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


University of Tennessee – Knoxville

12. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2021 Mar 03]. 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

13. 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 (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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Friedlander Y. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2021 Mar 03]. 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 Pretoria

14. 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 (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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC . [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2021 Mar 03]. 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

15. 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 March 03, 2021. http://hdl.handle.net/1957/41696.

MLA Handbook (7th Edition):

Vincent, Andrew M. “Fuel-cladding mechanical interaction in simulated sphere pac fuel.” 1981. Web. 03 Mar 2021.

Vancouver:

Vincent AM. Fuel-cladding mechanical interaction in simulated sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2021 Mar 03]. 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


Texas A&M University

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

Degree: MS, Nuclear Engineering, 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. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638

Chicago Manual of Style (16th Edition):

Hogelin, Thomas Russell. “Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.” 2011. Masters Thesis, Texas A&M University. Accessed March 03, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638.

MLA Handbook (7th Edition):

Hogelin, Thomas Russell. “Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing.” 2011. Web. 03 Mar 2021.

Vancouver:

Hogelin TR. Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. [Internet] [Masters thesis]. Texas A&M University; 2011. [cited 2021 Mar 03]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2010-12-8638.

Council of Science Editors:

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


University of Saskatchewan

17. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Oladimeji DJ1. Thermal Conductivity of Nuclear Fuel and its Degradation by Physical and Chemical Burnup. [Internet] [Thesis]. University of Saskatchewan; 2017. [cited 2021 Mar 03]. 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


University of Pretoria

18. 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 March 03, 2021. http://hdl.handle.net/2263/25616.

MLA Handbook (7th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC.” 2011. Web. 03 Mar 2021.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC. [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2021 Mar 03]. 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


Oregon State University

19. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Clark, R. G. (Robert Gilder) 1. Monitoring surface temperature of irradiated fuel elements. [Internet] [Masters thesis]. Oregon State University; 1963. [cited 2021 Mar 03]. 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

20. 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 March 03, 2021. 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. 03 Mar 2021.

Vancouver:

Latimer GD. Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2021 Mar 03]. 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 Ontario Institute of Technology

21. 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 March 03, 2021. 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. 03 Mar 2021.

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 2021 Mar 03]. 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


University of Tennessee – Knoxville

22. 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 March 03, 2021. 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. 03 Mar 2021.

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 2021 Mar 03]. 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


University of Cambridge

23. Charles, Alan. Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies.

Degree: PhD, 2020, University of Cambridge

 As pressure grows on developed nations to move away from fossil fuel-based energy sources, so does the potential for nuclear energy to make its resurgence.… (more)

Subjects/Keywords: Nuclear; Optimization; Differential Evolution; Fuel Assembly Design

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APA (6th Edition):

Charles, A. (2020). Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies. (Doctoral Dissertation). University of Cambridge. Retrieved from https://www.repository.cam.ac.uk/handle/1810/315342

Chicago Manual of Style (16th Edition):

Charles, Alan. “Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies.” 2020. Doctoral Dissertation, University of Cambridge. Accessed March 03, 2021. https://www.repository.cam.ac.uk/handle/1810/315342.

MLA Handbook (7th Edition):

Charles, Alan. “Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies.” 2020. Web. 03 Mar 2021.

Vancouver:

Charles A. Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies. [Internet] [Doctoral dissertation]. University of Cambridge; 2020. [cited 2021 Mar 03]. Available from: https://www.repository.cam.ac.uk/handle/1810/315342.

Council of Science Editors:

Charles A. Development of a Multi-Objective Optimization Capability for Heterogeneous Light Water Reactor Fuel Assemblies. [Doctoral Dissertation]. University of Cambridge; 2020. Available from: https://www.repository.cam.ac.uk/handle/1810/315342

24. Merwin, Augustus. Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide.

Degree: 2012, University of Nevada – Reno

 Reprocessing of spent nuclear fuel is an essential step in closing the nuclear fuel cycle. In order to consume current stockpiles, ceramic uranium dioxide spent… (more)

Subjects/Keywords: Corrosion; molten salt; nuclear fuel cycle; pyroprocessing

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APA (6th Edition):

Merwin, A. (2012). Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide. (Thesis). University of Nevada – Reno. Retrieved from http://hdl.handle.net/11714/3744

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):

Merwin, Augustus. “Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide.” 2012. Thesis, University of Nevada – Reno. Accessed March 03, 2021. http://hdl.handle.net/11714/3744.

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

MLA Handbook (7th Edition):

Merwin, Augustus. “Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide.” 2012. Web. 03 Mar 2021.

Vancouver:

Merwin A. Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide. [Internet] [Thesis]. University of Nevada – Reno; 2012. [cited 2021 Mar 03]. Available from: http://hdl.handle.net/11714/3744.

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

Council of Science Editors:

Merwin A. Alternative Anodes for the Electrolytic Reduction of Uranium Dioxide. [Thesis]. University of Nevada – Reno; 2012. Available from: http://hdl.handle.net/11714/3744

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


University of Cambridge

25. Charles, Alan. Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies.

Degree: PhD, 2020, University of Cambridge

 As pressure grows on developed nations to move away from fossil fuel-based energy sources, so does the potential for nuclear energy to make its resurgence.… (more)

Subjects/Keywords: Nuclear; Optimization; Differential Evolution; Fuel Assembly Design

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APA (6th Edition):

Charles, A. (2020). Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies. (Doctoral Dissertation). University of Cambridge. Retrieved from https://doi.org/10.17863/CAM.62450 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.821619

Chicago Manual of Style (16th Edition):

Charles, Alan. “Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies.” 2020. Doctoral Dissertation, University of Cambridge. Accessed March 03, 2021. https://doi.org/10.17863/CAM.62450 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.821619.

MLA Handbook (7th Edition):

Charles, Alan. “Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies.” 2020. Web. 03 Mar 2021.

Vancouver:

Charles A. Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies. [Internet] [Doctoral dissertation]. University of Cambridge; 2020. [cited 2021 Mar 03]. Available from: https://doi.org/10.17863/CAM.62450 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.821619.

Council of Science Editors:

Charles A. Development of a multi-objective optimization capability for heterogeneous light water reactor fuel assemblies. [Doctoral Dissertation]. University of Cambridge; 2020. Available from: https://doi.org/10.17863/CAM.62450 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.821619

26. 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 (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 March 03, 2021. 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. 03 Mar 2021.

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 2021 Mar 03]. 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

27. Ježek, Martin. Palivový cyklus jaderné elektrárny Temelín: Nuclear Fuel Cycle of Temelin NPP.

Degree: 2019, Brno University of Technology

 This bachelor's thesis deals with the central part of a fuel cycle in the power plant of Temelín. It describes generally the whole fuel cycle,… (more)

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

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APA (6th Edition):

Ježek, M. (2019). Palivový cyklus jaderné elektrárny Temelín: Nuclear Fuel Cycle of Temelin NPP. (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: Nuclear Fuel Cycle of Temelin NPP.” 2019. Thesis, Brno University of Technology. Accessed March 03, 2021. 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: Nuclear Fuel Cycle of Temelin NPP.” 2019. Web. 03 Mar 2021.

Vancouver:

Ježek M. Palivový cyklus jaderné elektrárny Temelín: Nuclear Fuel Cycle of Temelin NPP. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Mar 03]. 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: Nuclear Fuel Cycle of Temelin NPP. [Thesis]. Brno University of Technology; 2019. 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


Penn State University

28. Bratton, Ryan Nathaniel. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.

Degree: 2015, Penn State University

 The bias and uncertainty in fuel isotopic calculations for a well-defined radiochemical assay benchmark are investigated with Sampler, the new sampling-based uncertainty quantification tool in… (more)

Subjects/Keywords: SCALE; FRAPCON; rod internal pressure; fuel isotopics; spent nuclear fuel

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APA (6th Edition):

Bratton, R. N. (2015). Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27289

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):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Thesis, Penn State University. Accessed March 03, 2021. https://submit-etda.libraries.psu.edu/catalog/27289.

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

MLA Handbook (7th Edition):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Web. 03 Mar 2021.

Vancouver:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Mar 03]. Available from: https://submit-etda.libraries.psu.edu/catalog/27289.

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

Council of Science Editors:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27289

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


Georgia Tech

29. Kingsbury, Christopher W. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The fluoride-salt-cooled high-temperature reactor (FHR) is a novel reactor design benefitting from passive safety features, high operating temperatures with corresponding high conversion efficiency, to name… (more)

Subjects/Keywords: Nuclear fuel design; Fuel cycle cost; Advanced high temperature reactors

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APA (6th Edition):

Kingsbury, C. W. (2015). Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54337

Chicago Manual of Style (16th Edition):

Kingsbury, Christopher W. “Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.” 2015. Masters Thesis, Georgia Tech. Accessed March 03, 2021. http://hdl.handle.net/1853/54337.

MLA Handbook (7th Edition):

Kingsbury, Christopher W. “Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.” 2015. Web. 03 Mar 2021.

Vancouver:

Kingsbury CW. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2021 Mar 03]. Available from: http://hdl.handle.net/1853/54337.

Council of Science Editors:

Kingsbury CW. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/54337


University of South Carolina

30. Metzger, Kathryn Elizabeth. Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method.

Degree: MS, Nuclear Engineering, 2013, University of South Carolina

  In light of the disaster at the Fukushima Daiichi Nuclear Plant, the Department of Energy's Advanced Fuels Program has shifted its interest from enhanced… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Dispersion Fuel; Fabrication; Fuel Particles; Spark Erosion

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

APA (6th Edition):

Metzger, K. E. (2013). Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/2368

Chicago Manual of Style (16th Edition):

Metzger, Kathryn Elizabeth. “Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method.” 2013. Masters Thesis, University of South Carolina. Accessed March 03, 2021. https://scholarcommons.sc.edu/etd/2368.

MLA Handbook (7th Edition):

Metzger, Kathryn Elizabeth. “Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method.” 2013. Web. 03 Mar 2021.

Vancouver:

Metzger KE. Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method. [Internet] [Masters thesis]. University of South Carolina; 2013. [cited 2021 Mar 03]. Available from: https://scholarcommons.sc.edu/etd/2368.

Council of Science Editors:

Metzger KE. Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method. [Masters Thesis]. University of South Carolina; 2013. Available from: https://scholarcommons.sc.edu/etd/2368

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