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You searched for subject:(Nuclear fuel Nuclear reactor Chemical analysis). Showing records 1 – 30 of 126129 total matches.

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1. 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 June 16, 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. 16 Jun 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 Jun 16]. 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 ;


University of Texas – Austin

2. -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 June 16, 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. 16 Jun 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 Jun 16]. 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


McMaster University

3. McDonald, Michael H. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.

Degree: MASc, 2011, McMaster University

The supercritical water cooled reactor (SCWR) is a Generation IV reactor concept that features light water coolant in a supercritical state. Canada is developing… (more)

Subjects/Keywords: Reactor physics; supercritical water cooled reactor; fuel; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

McDonald, M. H. (2011). Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11223

Chicago Manual of Style (16th Edition):

McDonald, Michael H. “Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.” 2011. Masters Thesis, McMaster University. Accessed June 16, 2019. http://hdl.handle.net/11375/11223.

MLA Handbook (7th Edition):

McDonald, Michael H. “Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor.” 2011. Web. 16 Jun 2019.

Vancouver:

McDonald MH. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11375/11223.

Council of Science Editors:

McDonald MH. Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11223


Virginia Commonwealth University

4. 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 June 16, 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. 16 Jun 2019.

Vancouver:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 Jun 16]. 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 Pretoria

5. 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 June 16, 2019. http://hdl.handle.net/2263/25616.

MLA Handbook (7th Edition):

Hlatshwayo, Thulani Thokozani. “Diffusion of silver in 6H-SiC.” 2011. Web. 16 Jun 2019.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC. [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2019 Jun 16]. 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

6. 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 June 16, 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. 16 Jun 2019.

Vancouver:

Hlatshwayo TT. Diffusion of silver in 6H-SiC . [Internet] [Doctoral dissertation]. University of Pretoria; 2011. [cited 2019 Jun 16]. 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/


Texas A&M University

7. Sternat, Matthew Ryan 1982-. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.

Degree: 2012, Texas A&M University

 Pre-detonation technical nuclear forensics techniques for research reactor spent fuel were developed in a collaborative project with Savannah River National Lab ratory. An inverse analysis(more)

Subjects/Keywords: Attribution; Spent Fuel; Research Reactor; Savannah River National Laboratory; Radiochemical Analysis; Inverse Reactor Physics; Inverse Problems; Nuclear Forensics

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APA (6th Edition):

Sternat, M. R. 1. (2012). Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/148202

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):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Thesis, Texas A&M University. Accessed June 16, 2019. http://hdl.handle.net/1969.1/148202.

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

MLA Handbook (7th Edition):

Sternat, Matthew Ryan 1982-. “Development of Technical Nuclear Forensics for Spent Research Reactor Fuel.” 2012. Web. 16 Jun 2019.

Vancouver:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1969.1/148202.

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

Council of Science Editors:

Sternat MR1. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/148202

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


Georgia Tech

8. Huning, Alexander Jared. A novel core analysis method for prismatic high temperature gas reactors.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 A new transient thermal hydraulic method for simulating prismatic HTGRs during a loss-of-forced-circulation (LOFC) accident is presented. This expands upon the steady state thermal hydraulic… (more)

Subjects/Keywords: HTGR; Thermal hydraulics; Reactor analysis; Nuclear safety

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APA (6th Edition):

Huning, A. J. (2016). A novel core analysis method for prismatic high temperature gas reactors. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58615

Chicago Manual of Style (16th Edition):

Huning, Alexander Jared. “A novel core analysis method for prismatic high temperature gas reactors.” 2016. Doctoral Dissertation, Georgia Tech. Accessed June 16, 2019. http://hdl.handle.net/1853/58615.

MLA Handbook (7th Edition):

Huning, Alexander Jared. “A novel core analysis method for prismatic high temperature gas reactors.” 2016. Web. 16 Jun 2019.

Vancouver:

Huning AJ. A novel core analysis method for prismatic high temperature gas reactors. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1853/58615.

Council of Science Editors:

Huning AJ. A novel core analysis method for prismatic high temperature gas reactors. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/58615


Brno University of Technology

9. Blažková, Eva. Přehled jaderných reaktorů světa .

Degree: 2010, Brno University of Technology

 Tato bakalářská práce se zabývá vytvořením přehledu typů jaderných reaktorů, jejich rozdělení a technické řešení vybraných typů. V práci je dále uvedeno zastoupení jednotlivých států,… (more)

Subjects/Keywords: jaderný reaktor; jaderná elektrárna; jaderná reakce; jaderné palivo; energetika; nuclear reactor; nuclear power plant; nuclear reaction; nuclear fuel; power supply

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APA (6th Edition):

Blažková, E. (2010). Přehled jaderných reaktorů světa . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/11747

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):

Blažková, Eva. “Přehled jaderných reaktorů světa .” 2010. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/11747.

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

MLA Handbook (7th Edition):

Blažková, Eva. “Přehled jaderných reaktorů světa .” 2010. Web. 16 Jun 2019.

Vancouver:

Blažková E. Přehled jaderných reaktorů světa . [Internet] [Thesis]. Brno University of Technology; 2010. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/11747.

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

Council of Science Editors:

Blažková E. Přehled jaderných reaktorů světa . [Thesis]. Brno University of Technology; 2010. Available from: http://hdl.handle.net/11012/11747

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


University of California – Irvine

10. Travis, Austin. Thermal Conductivity and Kapitza Resistance of Ceramic Composites.

Degree: Chemical and Biochemical Engineering, 2018, University of California – Irvine

 Advanced ceramic composites are actively investigated for use in various fields of the technology sector including nuclear fuel. Conventional uranium dioxide (UO2) nuclear fuel has… (more)

Subjects/Keywords: Chemical engineering; Materials Science; Nuclear engineering; Ceramics; Composites; Finite Element Analysis; Kapitza Resistance; Nuclear Fuel; Thermal Conductivity

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APA (6th Edition):

Travis, A. (2018). Thermal Conductivity and Kapitza Resistance of Ceramic Composites. (Thesis). University of California – Irvine. Retrieved from http://www.escholarship.org/uc/item/1r3405wr

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):

Travis, Austin. “Thermal Conductivity and Kapitza Resistance of Ceramic Composites.” 2018. Thesis, University of California – Irvine. Accessed June 16, 2019. http://www.escholarship.org/uc/item/1r3405wr.

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

MLA Handbook (7th Edition):

Travis, Austin. “Thermal Conductivity and Kapitza Resistance of Ceramic Composites.” 2018. Web. 16 Jun 2019.

Vancouver:

Travis A. Thermal Conductivity and Kapitza Resistance of Ceramic Composites. [Internet] [Thesis]. University of California – Irvine; 2018. [cited 2019 Jun 16]. Available from: http://www.escholarship.org/uc/item/1r3405wr.

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

Council of Science Editors:

Travis A. Thermal Conductivity and Kapitza Resistance of Ceramic Composites. [Thesis]. University of California – Irvine; 2018. Available from: http://www.escholarship.org/uc/item/1r3405wr

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


University of Ghana

11. Ojo, O.P. Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor .

Degree: 2018, University of Ghana

 The European Pressurized Water Reactor (EPR) and Hualong One Pressurized Water Reactor (HPR) are two of the reactors under consideration by the Ghana Nuclear Power… (more)

Subjects/Keywords: Investigative Study; Radiotoxicity; Nuclear Fuel; Power Plants; Commercial Nuclear; European Pressurized; Water Reactor and Hualong

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APA (6th Edition):

Ojo, O. P. (2018). Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor . (Masters Thesis). University of Ghana. Retrieved from http://ugspace.ug.edu.gh/handle/123456789/26840

Chicago Manual of Style (16th Edition):

Ojo, O P. “Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor .” 2018. Masters Thesis, University of Ghana. Accessed June 16, 2019. http://ugspace.ug.edu.gh/handle/123456789/26840.

MLA Handbook (7th Edition):

Ojo, O P. “Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor .” 2018. Web. 16 Jun 2019.

Vancouver:

Ojo OP. Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor . [Internet] [Masters thesis]. University of Ghana; 2018. [cited 2019 Jun 16]. Available from: http://ugspace.ug.edu.gh/handle/123456789/26840.

Council of Science Editors:

Ojo OP. Investigative Study of Radiotoxicity of Spent Nuclear Fuel Assembly of Some Commercial Nuclear Power Plants Case Study: European Pressurized Water Reactor and Hualong One Pressurized Water Reactor . [Masters Thesis]. University of Ghana; 2018. Available from: http://ugspace.ug.edu.gh/handle/123456789/26840


University of Ghana

12. Essel, P.A.A. Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) .

Degree: 2016, University of Ghana

 Ghana is in the process of converting its fuel from Highly Enriched Uranium (HEU) to Lowly Enriched Uranium (LEU) even though the HEU fuel is… (more)

Subjects/Keywords: Dose Rate; Nuclear Fuel; Ghana Research Reactor-1 (Gharr-1)

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APA (6th Edition):

Essel, P. A. A. (2016). Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) . (Masters Thesis). University of Ghana. Retrieved from http://ugspace.ug.edu.gh/handle/123456789/21630

Chicago Manual of Style (16th Edition):

Essel, P A A. “Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) .” 2016. Masters Thesis, University of Ghana. Accessed June 16, 2019. http://ugspace.ug.edu.gh/handle/123456789/21630.

MLA Handbook (7th Edition):

Essel, P A A. “Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) .” 2016. Web. 16 Jun 2019.

Vancouver:

Essel PAA. Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) . [Internet] [Masters thesis]. University of Ghana; 2016. [cited 2019 Jun 16]. Available from: http://ugspace.ug.edu.gh/handle/123456789/21630.

Council of Science Editors:

Essel PAA. Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (Gharr-1) . [Masters Thesis]. University of Ghana; 2016. Available from: http://ugspace.ug.edu.gh/handle/123456789/21630


University of Pretoria

13. Noah, Olugbenga Olanrewaju. Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry.

Degree: PhD, Mechanical and Aeronautical Engineering, 2017, University of Pretoria

 The ability of coated particles of enriched uranium dioxide (UO2) fuel to withstand high temperatures and contain the fission products in the case of a… (more)

Subjects/Keywords: UCTD; Nuclear fuel; Light-water reactor; Porous medium; Numerical simulation

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APA (6th Edition):

Noah, O. (2017). Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry. (Doctoral Dissertation). University of Pretoria. Retrieved from http://hdl.handle.net/2263/61321

Chicago Manual of Style (16th Edition):

Noah, Olugbenga. “Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry.” 2017. Doctoral Dissertation, University of Pretoria. Accessed June 16, 2019. http://hdl.handle.net/2263/61321.

MLA Handbook (7th Edition):

Noah, Olugbenga. “Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry.” 2017. Web. 16 Jun 2019.

Vancouver:

Noah O. Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry. [Internet] [Doctoral dissertation]. University of Pretoria; 2017. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/2263/61321.

Council of Science Editors:

Noah O. Experimental theoretical and numerical investigation of natural convection heat transfer from heated micro-spheres in a slender cylindrical geometry. [Doctoral Dissertation]. University of Pretoria; 2017. Available from: http://hdl.handle.net/2263/61321


University of Illinois – Urbana-Champaign

14. Bae, Jin Whan. Fuel cycle transition simulation capabilities in CYCLUS.

Degree: MS, Nuclear, Plasma, Radiolgc Engr, 2018, University of Illinois – Urbana-Champaign

 Recent interest in advanced reactors and the following need for techno-economic transitions has increased the demand for tools necessary to model complex nuclear fuel cycles… (more)

Subjects/Keywords: Nuclear Fuel Cycle; Molten Salt Reactor; Cyclus; Transition Scenario

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APA (6th Edition):

Bae, J. W. (2018). Fuel cycle transition simulation capabilities in CYCLUS. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/102517

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):

Bae, Jin Whan. “Fuel cycle transition simulation capabilities in CYCLUS.” 2018. Thesis, University of Illinois – Urbana-Champaign. Accessed June 16, 2019. http://hdl.handle.net/2142/102517.

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

MLA Handbook (7th Edition):

Bae, Jin Whan. “Fuel cycle transition simulation capabilities in CYCLUS.” 2018. Web. 16 Jun 2019.

Vancouver:

Bae JW. Fuel cycle transition simulation capabilities in CYCLUS. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2018. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/2142/102517.

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

Council of Science Editors:

Bae JW. Fuel cycle transition simulation capabilities in CYCLUS. [Thesis]. University of Illinois – Urbana-Champaign; 2018. Available from: http://hdl.handle.net/2142/102517

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


University of Cambridge

15. Lindley, Benjamin A. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.

Degree: PhD, 2015, University of Cambridge

 Light water reactors (LWRs) are the world’s dominant nuclear reactor system. Uranium (U)-fuelled LWRs produce long-lived transuranic (TRU) isotopes. TRUs can be recycled in LWRs… (more)

Subjects/Keywords: 539.7; Thorium; Light Water Reactor; Plutonium; Transuranic; Reduced-moderation; Nuclear fuel cycle; Reactor physics

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APA (6th Edition):

Lindley, B. A. (2015). The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. (Doctoral Dissertation). University of Cambridge. Retrieved from https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470

Chicago Manual of Style (16th Edition):

Lindley, Benjamin A. “The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.” 2015. Doctoral Dissertation, University of Cambridge. Accessed June 16, 2019. https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470.

MLA Handbook (7th Edition):

Lindley, Benjamin A. “The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel.” 2015. Web. 16 Jun 2019.

Vancouver:

Lindley BA. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. [Internet] [Doctoral dissertation]. University of Cambridge; 2015. [cited 2019 Jun 16]. Available from: https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470.

Council of Science Editors:

Lindley BA. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel. [Doctoral Dissertation]. University of Cambridge; 2015. Available from: https://www.repository.cam.ac.uk/handle/1810/247162 ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.642470


University of California – Irvine

16. Jackson, Andy Steven. An Investigation of Aggregation in Synergistic Solvent Extraction Systems.

Degree: Chemical and Biochemical Engineering, 2017, University of California – Irvine

 With an increasing focus on anthropogenic climate change, nuclear reactors present an attractive option for base load power generation with regard to air pollution and… (more)

Subjects/Keywords: Chemical engineering; Nuclear chemistry; Radiochemistry; Reprocessing; Solvent Extraction; Used Nuclear Fuel

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APA (6th Edition):

Jackson, A. S. (2017). An Investigation of Aggregation in Synergistic Solvent Extraction Systems. (Thesis). University of California – Irvine. Retrieved from http://www.escholarship.org/uc/item/35d4x8gx

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):

Jackson, Andy Steven. “An Investigation of Aggregation in Synergistic Solvent Extraction Systems.” 2017. Thesis, University of California – Irvine. Accessed June 16, 2019. http://www.escholarship.org/uc/item/35d4x8gx.

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

MLA Handbook (7th Edition):

Jackson, Andy Steven. “An Investigation of Aggregation in Synergistic Solvent Extraction Systems.” 2017. Web. 16 Jun 2019.

Vancouver:

Jackson AS. An Investigation of Aggregation in Synergistic Solvent Extraction Systems. [Internet] [Thesis]. University of California – Irvine; 2017. [cited 2019 Jun 16]. Available from: http://www.escholarship.org/uc/item/35d4x8gx.

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

Council of Science Editors:

Jackson AS. An Investigation of Aggregation in Synergistic Solvent Extraction Systems. [Thesis]. University of California – Irvine; 2017. Available from: http://www.escholarship.org/uc/item/35d4x8gx

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


Iowa State University

17. Burchell, Gail Patrick. Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly.

Degree: 1967, Iowa State University

Subjects/Keywords: Nuclear reactors; Nuclear fuel elements; Reactor moderators; Nuclear Engineering

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APA (6th Edition):

Burchell, G. P. (1967). Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly. (Thesis). Iowa State University. Retrieved from https://lib.dr.iastate.edu/rtd/18822

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):

Burchell, Gail Patrick. “Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly.” 1967. Thesis, Iowa State University. Accessed June 16, 2019. https://lib.dr.iastate.edu/rtd/18822.

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

MLA Handbook (7th Edition):

Burchell, Gail Patrick. “Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly.” 1967. Web. 16 Jun 2019.

Vancouver:

Burchell GP. Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly. [Internet] [Thesis]. Iowa State University; 1967. [cited 2019 Jun 16]. Available from: https://lib.dr.iastate.edu/rtd/18822.

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

Council of Science Editors:

Burchell GP. Preliminary design and lattice optimization for natural uranium, light water moderated, subcritical assembly. [Thesis]. Iowa State University; 1967. Available from: https://lib.dr.iastate.edu/rtd/18822

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


MIT

18. McCauley, John Jay. A review of the MITR-II basis accident .

Degree: Department of Nuclear Engineering, 1982, MIT

Subjects/Keywords: Nuclear Engineering.; Nuclear reactor accidents; Nuclear fuel elements

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APA (6th Edition):

McCauley, J. J. (1982). A review of the MITR-II basis accident . (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/104158

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):

McCauley, John Jay. “A review of the MITR-II basis accident .” 1982. Thesis, MIT. Accessed June 16, 2019. http://hdl.handle.net/1721.1/104158.

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

MLA Handbook (7th Edition):

McCauley, John Jay. “A review of the MITR-II basis accident .” 1982. Web. 16 Jun 2019.

Vancouver:

McCauley JJ. A review of the MITR-II basis accident . [Internet] [Thesis]. MIT; 1982. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1721.1/104158.

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

Council of Science Editors:

McCauley JJ. A review of the MITR-II basis accident . [Thesis]. MIT; 1982. Available from: http://hdl.handle.net/1721.1/104158

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


Brno University of Technology

19. Mlčúch, Adam. Jaderné reaktory 4. generace .

Degree: 2012, Brno University of Technology

 Tato bakalářská práce se zabývá vytvořením přehledu jednotlivých generací jaderných reaktorů. Největší část práce je následně věnovaná reaktorovým systémům čtvrté generace. Jednotlivé návrhy vycházejí ze… (more)

Subjects/Keywords: jaderný reaktor; čtvrtá generace; jaderná elektrárna; jaderné palivo; energetika; nuclear reactor; generation four; nuclear power plant; nuclear fuel

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APA (6th Edition):

Mlčúch, A. (2012). Jaderné reaktory 4. generace . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/10242

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):

Mlčúch, Adam. “Jaderné reaktory 4. generace .” 2012. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/10242.

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

MLA Handbook (7th Edition):

Mlčúch, Adam. “Jaderné reaktory 4. generace .” 2012. Web. 16 Jun 2019.

Vancouver:

Mlčúch A. Jaderné reaktory 4. generace . [Internet] [Thesis]. Brno University of Technology; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/10242.

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

Council of Science Editors:

Mlčúch A. Jaderné reaktory 4. generace . [Thesis]. Brno University of Technology; 2012. Available from: http://hdl.handle.net/11012/10242

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


Brno University of Technology

20. Kadlec, Miroslav. Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů .

Degree: 2013, Brno University of Technology

 Tato Bakalářská práce se zaměřuje na vývoj jaderných reaktorů a na paliva v nich spalované. Jsou zde popsány jednotlivé druhy jaderných paliv včetně způsobů, jak… (more)

Subjects/Keywords: Jaderná elektrárna; Jaderný reaktor; Jaderné palivo; JHR; MYRRHA; ALLEGRO; BREST; nuclear power; nuclear reactor; nuclear fuel; JHR; MYRRHA; ALLEGRO; BREST

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APA (6th Edition):

Kadlec, M. (2013). Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/26833

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):

Kadlec, Miroslav. “Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů .” 2013. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/26833.

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

MLA Handbook (7th Edition):

Kadlec, Miroslav. “Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů .” 2013. Web. 16 Jun 2019.

Vancouver:

Kadlec M. Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů . [Internet] [Thesis]. Brno University of Technology; 2013. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/26833.

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

Council of Science Editors:

Kadlec M. Perspektivní jaderná paliva pro pokročilé typy jaderných reaktorů . [Thesis]. Brno University of Technology; 2013. Available from: http://hdl.handle.net/11012/26833

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


Brno University of Technology

21. Katzer, Milan. Jaderné reaktory 4.generace .

Degree: 2011, Brno University of Technology

 Tato bakalářská práce se zabývá vytvořením přehledu jednotlivých generací jaderných reaktorů. Největší část práce, je pak věnována revolučním projektům reaktorů IV. generace, určených pro nasazení… (more)

Subjects/Keywords: jaderný reaktor; čtvrtá generace; jaderná elektrárna; jaderné palivo; energetika; nuclear reactor; GIF; nuclear power plant; nuclear fuel; power supply

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APA (6th Edition):

Katzer, M. (2011). Jaderné reaktory 4.generace . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/15822

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):

Katzer, Milan. “Jaderné reaktory 4.generace .” 2011. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/15822.

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

MLA Handbook (7th Edition):

Katzer, Milan. “Jaderné reaktory 4.generace .” 2011. Web. 16 Jun 2019.

Vancouver:

Katzer M. Jaderné reaktory 4.generace . [Internet] [Thesis]. Brno University of Technology; 2011. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/15822.

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

Council of Science Editors:

Katzer M. Jaderné reaktory 4.generace . [Thesis]. Brno University of Technology; 2011. Available from: http://hdl.handle.net/11012/15822

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


Brno University of Technology

22. Šimík, Michal. Moderní jaderné reaktory .

Degree: 2013, Brno University of Technology

 Táto bakalárska práca sa zaoberá vytvorením prehľadu typov jadrových reaktorov, ich históriou, súčasnosťou aj budúcnosťou. Veľká časť je zameraná na ciele požadované od moderných jadrových… (more)

Subjects/Keywords: Jadrový reaktor; jadrová elektráreň; štvrtá generácia; moderátor; chladivo; jadrové palivo; jadrová reakcia; jadrový odpad; Nuclear reactor; nuclear power plant; fourth generation; moderator; coolant; nuclear fuel; nuclear fission; nuclear waste

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APA (6th Edition):

Šimík, M. (2013). Moderní jaderné reaktory . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/27446

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):

Šimík, Michal. “Moderní jaderné reaktory .” 2013. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/27446.

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

MLA Handbook (7th Edition):

Šimík, Michal. “Moderní jaderné reaktory .” 2013. Web. 16 Jun 2019.

Vancouver:

Šimík M. Moderní jaderné reaktory . [Internet] [Thesis]. Brno University of Technology; 2013. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/27446.

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

Council of Science Editors:

Šimík M. Moderní jaderné reaktory . [Thesis]. Brno University of Technology; 2013. Available from: http://hdl.handle.net/11012/27446

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


McMaster University

23. Morreale, Andrew C. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.

Degree: PhD, 2012, McMaster University

The reprocessing of spent fuel is a key component in reducing the end waste from nuclear power plant operations and creating a sustainable closed… (more)

Subjects/Keywords: CANDU; Actinide Burning; Nuclear Safety Analysis; Mixed Oxide Fuel; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Morreale, A. C. (2012). Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/12784

Chicago Manual of Style (16th Edition):

Morreale, Andrew C. “Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.” 2012. Doctoral Dissertation, McMaster University. Accessed June 16, 2019. http://hdl.handle.net/11375/12784.

MLA Handbook (7th Edition):

Morreale, Andrew C. “Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.” 2012. Web. 16 Jun 2019.

Vancouver:

Morreale AC. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. [Internet] [Doctoral dissertation]. McMaster University; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11375/12784.

Council of Science Editors:

Morreale AC. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. [Doctoral Dissertation]. McMaster University; 2012. Available from: http://hdl.handle.net/11375/12784


McMaster University

24. McEwan, Curtis E. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.

Degree: MASc, 2013, McMaster University

Simulation plays a key role in nuclear reactor safety analysis and being able to assess the accuracy of results obtained by simulation increases their… (more)

Subjects/Keywords: Reactor Physics; Covariance; Uncertainty Analysis; Total Monte Carlo; Dilution; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

McEwan, C. E. (2013). Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/13396

Chicago Manual of Style (16th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Masters Thesis, McMaster University. Accessed June 16, 2019. http://hdl.handle.net/11375/13396.

MLA Handbook (7th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Web. 16 Jun 2019.

Vancouver:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11375/13396.

Council of Science Editors:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Masters Thesis]. McMaster University; 2013. Available from: http://hdl.handle.net/11375/13396


University of Michigan

25. Young, Mitchell. Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis.

Degree: PhD, Nuclear Engineering & Radiological Sciences, 2016, University of Michigan

 Solutions to the Boltzmann transport equation are an important starting point for many aspects of nuclear reactor design and analysis. Many interesting physical phenomena depend… (more)

Subjects/Keywords: nuclear reactor analysis; method of characteristics; Nuclear Engineering and Radiological Sciences; Engineering

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APA (6th Edition):

Young, M. (2016). Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis. (Doctoral Dissertation). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/135759

Chicago Manual of Style (16th Edition):

Young, Mitchell. “Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis.” 2016. Doctoral Dissertation, University of Michigan. Accessed June 16, 2019. http://hdl.handle.net/2027.42/135759.

MLA Handbook (7th Edition):

Young, Mitchell. “Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis.” 2016. Web. 16 Jun 2019.

Vancouver:

Young M. Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis. [Internet] [Doctoral dissertation]. University of Michigan; 2016. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/2027.42/135759.

Council of Science Editors:

Young M. Orthogonal-Mesh, 3D Sn with Embedded 2-D Method of Characteristics for Whole-Core, Pin-Resolved Reactor Analysis. [Doctoral Dissertation]. University of Michigan; 2016. Available from: http://hdl.handle.net/2027.42/135759


University of California – Berkeley

26. Heidet, Florent. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.

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

 The primary objective of this study was to estimate the maximum fuel utilization that is achievable using fast reactors that are designed to operate with… (more)

Subjects/Keywords: Nuclear Engineering; Breed and burn; Burnup; Fast reactor; Fuel cycle; Generation IV; Uranium utilization

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APA (6th Edition):

Heidet, F. (2010). Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/63j4k05n

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):

Heidet, Florent. “Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.” 2010. Thesis, University of California – Berkeley. Accessed June 16, 2019. http://www.escholarship.org/uc/item/63j4k05n.

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

MLA Handbook (7th Edition):

Heidet, Florent. “Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.” 2010. Web. 16 Jun 2019.

Vancouver:

Heidet F. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2019 Jun 16]. Available from: http://www.escholarship.org/uc/item/63j4k05n.

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

Council of Science Editors:

Heidet F. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. [Thesis]. University of California – Berkeley; 2010. Available from: http://www.escholarship.org/uc/item/63j4k05n

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


McMaster University

27. Younan, Simon. Comparative study of accident-tolerant fuel for a CANDU lattice.

Degree: MASc, 2017, McMaster University

McMaster University MASTER OF APPLIED SCIENCES (2017) Hamilton, Ontario (Engineering Physics) TITLE: Comparative study of accident-tolerant fuel for a CANDU lattice AUTHOR: Simon Younan, B.Eng.… (more)

Subjects/Keywords: nuclear engineering; reactor physics; CANDU; accident-tolerant fuel; Serpent 2; Monte Carlo; accident-tolerant cladding

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APA (6th Edition):

Younan, S. (2017). Comparative study of accident-tolerant fuel for a CANDU lattice. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/22194

Chicago Manual of Style (16th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Masters Thesis, McMaster University. Accessed June 16, 2019. http://hdl.handle.net/11375/22194.

MLA Handbook (7th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Web. 16 Jun 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11375/22194.

Council of Science Editors:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22194


Texas A&M University

28. Gerhart, Jeremy Jens. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.

Degree: 2015, Texas A&M University

 There is a need for a technique that is able to quickly and accurately quantify the amount of 239Pu in spent nuclear fuel. With the… (more)

Subjects/Keywords: nuclear; resonance; fluorescence; nrf; cog; plutonium; mega-ray; spent fuel; pressurized water reactor; pwr

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APA (6th Edition):

Gerhart, J. J. (2015). Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156269

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):

Gerhart, Jeremy Jens. “Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.” 2015. Thesis, Texas A&M University. Accessed June 16, 2019. http://hdl.handle.net/1969.1/156269.

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

MLA Handbook (7th Edition):

Gerhart, Jeremy Jens. “Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.” 2015. Web. 16 Jun 2019.

Vancouver:

Gerhart JJ. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. [Internet] [Thesis]. Texas A&M University; 2015. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1969.1/156269.

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

Council of Science Editors:

Gerhart JJ. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. [Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/156269

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


University of South Carolina

29. Read Jr., Carey McIlwaine. Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor.

Degree: MS, Nuclear Engineering, 2011, University of South Carolina

  Fast reactors containing heterogeneous minor actinide target rods are now being modeled. When studying transmutation in these rods, helium production from α-decay must be… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Fuel Cycle; Helium Production; Heterogeneous Burner Reactor; Minor Actinide; SCHIBR; Transmutation

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APA (6th Edition):

Read Jr., C. M. (2011). Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/1670

Chicago Manual of Style (16th Edition):

Read Jr., Carey McIlwaine. “Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor.” 2011. Masters Thesis, University of South Carolina. Accessed June 16, 2019. https://scholarcommons.sc.edu/etd/1670.

MLA Handbook (7th Edition):

Read Jr., Carey McIlwaine. “Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor.” 2011. Web. 16 Jun 2019.

Vancouver:

Read Jr. CM. Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor. [Internet] [Masters thesis]. University of South Carolina; 2011. [cited 2019 Jun 16]. Available from: https://scholarcommons.sc.edu/etd/1670.

Council of Science Editors:

Read Jr. CM. Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor. [Masters Thesis]. University of South Carolina; 2011. Available from: https://scholarcommons.sc.edu/etd/1670


Brno University of Technology

30. Smetana, Jan. Jaderná paliva pro tlakovodní jaderné reaktory .

Degree: 2014, Brno University of Technology

 Tato bakalářská práce se zabývá konstrukčními vlastnostmi jaderných paliv, pozornost je věnována zejména palivům pro tlakovodní reaktory. Pro lepší představu čtenáře jsou uvedeny rovněž příklady… (more)

Subjects/Keywords: jaderné palivo; Dukovany; Temelín; tlakovodní reaktor; VVER; nuclear fuel; Dukovany; Temelin; pressurized water reactor; VVER

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

APA (6th Edition):

Smetana, J. (2014). Jaderná paliva pro tlakovodní jaderné reaktory . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/34334

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):

Smetana, Jan. “Jaderná paliva pro tlakovodní jaderné reaktory .” 2014. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/34334.

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

MLA Handbook (7th Edition):

Smetana, Jan. “Jaderná paliva pro tlakovodní jaderné reaktory .” 2014. Web. 16 Jun 2019.

Vancouver:

Smetana J. Jaderná paliva pro tlakovodní jaderné reaktory . [Internet] [Thesis]. Brno University of Technology; 2014. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/34334.

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

Council of Science Editors:

Smetana J. Jaderná paliva pro tlakovodní jaderné reaktory . [Thesis]. Brno University of Technology; 2014. Available from: http://hdl.handle.net/11012/34334

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

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