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You searched for subject:(Uranium silicide). Showing records 1 – 5 of 5 total matches.

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Georgia Tech

1. Burns, Joseph R. Reactivity control of a PWR 19x19 uranium silicide fuel assembly.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The Integral Inherently Safe Light Water Reactor (I2S-LWR) is a novel reactor concept which aims to apply safety-promoting features typical of small modular reactors (SMRs)… (more)

Subjects/Keywords: Reactivity control; Uranium silicide

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APA (6th Edition):

Burns, J. R. (2015). Reactivity control of a PWR 19x19 uranium silicide fuel assembly. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53975

Chicago Manual of Style (16th Edition):

Burns, Joseph R. “Reactivity control of a PWR 19x19 uranium silicide fuel assembly.” 2015. Masters Thesis, Georgia Tech. Accessed April 19, 2019. http://hdl.handle.net/1853/53975.

MLA Handbook (7th Edition):

Burns, Joseph R. “Reactivity control of a PWR 19x19 uranium silicide fuel assembly.” 2015. Web. 19 Apr 2019.

Vancouver:

Burns JR. Reactivity control of a PWR 19x19 uranium silicide fuel assembly. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 19]. Available from: http://hdl.handle.net/1853/53975.

Council of Science Editors:

Burns JR. Reactivity control of a PWR 19x19 uranium silicide fuel assembly. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/53975


Missouri University of Science and Technology

2. Prewitt, Benjamin Joseph. Analysis and implementation of accident tolerant nuclear fuels.

Degree: M.S. in Nuclear Engineering, Nuclear Engineering, Missouri University of Science and Technology

  "To improve the reliability and robustness of LWR, accident tolerant nuclear fuels and cladding materials are being developed to possibly replace the current UO2/zirconium… (more)

Subjects/Keywords: Advanced Fuels Campaign; Uranium Nitride; Uranium Silicide; Nuclear Engineering

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APA (6th Edition):

Prewitt, B. J. (n.d.). Analysis and implementation of accident tolerant nuclear fuels. (Masters Thesis). Missouri University of Science and Technology. Retrieved from http://scholarsmine.mst.edu/masters_theses/7657

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Chicago Manual of Style (16th Edition):

Prewitt, Benjamin Joseph. “Analysis and implementation of accident tolerant nuclear fuels.” Masters Thesis, Missouri University of Science and Technology. Accessed April 19, 2019. http://scholarsmine.mst.edu/masters_theses/7657.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

MLA Handbook (7th Edition):

Prewitt, Benjamin Joseph. “Analysis and implementation of accident tolerant nuclear fuels.” Web. 19 Apr 2019.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Vancouver:

Prewitt BJ. Analysis and implementation of accident tolerant nuclear fuels. [Internet] [Masters thesis]. Missouri University of Science and Technology; [cited 2019 Apr 19]. Available from: http://scholarsmine.mst.edu/masters_theses/7657.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Council of Science Editors:

Prewitt BJ. Analysis and implementation of accident tolerant nuclear fuels. [Masters Thesis]. Missouri University of Science and Technology; Available from: http://scholarsmine.mst.edu/masters_theses/7657

Note: this citation may be lacking information needed for this citation format:
No year of publication.

3. Uygur, Selim. Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments.

Degree: Reactor Physics, 2016, KTH

  During an extended LOCA in a LWR, the current UO2 fuel reaches very high temperatures and eventually melts, while the current Zircaloy fuel cladding… (more)

Subjects/Keywords: Uranium Mononitride; Uranium Silicide; Composite; Steam degradation; corrosion mechanism

…of ATFs to UO2[5] 12 2.3 Uranium Silicide (U3Si2) There are various… …beginning of the 2020s [1]. Uranium Mononitride (UN) is currently one of the… …expected in a live reactor core. 2.2 Uranium Mononitride (UN) UN’s thermal… …with novel claddings like steels [22]. The Uranium‒Nitrogen phase diagram for p… …diagram[23] Figure 2:Uranium‒Nitrogen phase diagram for p(N2) of 1 atm [… 

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APA (6th Edition):

Uygur, S. (2016). Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments. (Thesis). KTH. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-191366

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):

Uygur, Selim. “Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments.” 2016. Thesis, KTH. Accessed April 19, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-191366.

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

MLA Handbook (7th Edition):

Uygur, Selim. “Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments.” 2016. Web. 19 Apr 2019.

Vancouver:

Uygur S. Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments. [Internet] [Thesis]. KTH; 2016. [cited 2019 Apr 19]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-191366.

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

Council of Science Editors:

Uygur S. Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments. [Thesis]. KTH; 2016. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-191366

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

4. Winter, Thomas Christopher. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.

Degree: MS, Mechanical Engineering, 2016, Georgia Tech

 Theoretical models are used in support of the I2S-LWR (Integral Inherently Safe LWR) project for a direct comparison of fuel swelling and fission gas bubble… (more)

Subjects/Keywords: Fission gas swelling; Fuel swelling; Uranium silicide; Nuclear fuel swelling; Fission gas evolution; Swelling model; Nuclear fuel

Uranium silicide rapidly becomes amorphous under irradiation[4]. The di↵erent… …ix CHAPTER I INTRODUCTION Uranium silicide (U3 Si2 ) is being examined for… …doses.[4] The uranium silicide model, developed by Dr. J. Rest[20], with… …the fuel in a amorphous state was used. Since uranium silicide rapidly becomes amorphous… …of fuel swelling and fission gas bubble formation between U3 Si2 and UO2 fuels. Uranium… 

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APA (6th Edition):

Winter, T. C. (2016). Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54991

Chicago Manual of Style (16th Edition):

Winter, Thomas Christopher. “Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.” 2016. Masters Thesis, Georgia Tech. Accessed April 19, 2019. http://hdl.handle.net/1853/54991.

MLA Handbook (7th Edition):

Winter, Thomas Christopher. “Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.” 2016. Web. 19 Apr 2019.

Vancouver:

Winter TC. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. [Internet] [Masters thesis]. Georgia Tech; 2016. [cited 2019 Apr 19]. Available from: http://hdl.handle.net/1853/54991.

Council of Science Editors:

Winter TC. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. [Masters Thesis]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/54991


University of Florida

5. Franca, Romel Siqueira. Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods.

Degree: MS, Nuclear Engineering Sciences - Nuclear and Radiological Engineering, 2012, University of Florida

 This research presents the characterization, modeling, and design of the UFTR (University of Florida Training Reactor) radiation beam ports for reactor analysis applications. Extensive validation… (more)

Subjects/Keywords: Boxes; Collimators; Geometry; Graphite; Neutron spectra; Neutrons; Radiation beams; Reaction kinetics; Reactor cores; Thermal neutrons; 47  – barytes  – beam  – bias  – card  – carlo  – collimator  – concrete  – criticality  – definition  – distribution  – energy  – equation  – fission  – fixed  – flux  – foil  – geometry  – gold  – groups  – imp  – kcode  – mcnp  – method  – moderator  – monte  – neutron  – nonanalog  – phys  – port  – rate  – reaction  – read  – reduction  – roulette  – russian  – sdef  – silicide  – source  – spectrum  – splitting  – ssr  – ssw  – surface  – survival  – uftr  – uranium  – variance  – watt  – write

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

APA (6th Edition):

Franca, R. S. (2012). Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods. (Masters Thesis). University of Florida. Retrieved from http://ufdc.ufl.edu/UFE0044814

Chicago Manual of Style (16th Edition):

Franca, Romel Siqueira. “Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods.” 2012. Masters Thesis, University of Florida. Accessed April 19, 2019. http://ufdc.ufl.edu/UFE0044814.

MLA Handbook (7th Edition):

Franca, Romel Siqueira. “Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods.” 2012. Web. 19 Apr 2019.

Vancouver:

Franca RS. Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods. [Internet] [Masters thesis]. University of Florida; 2012. [cited 2019 Apr 19]. Available from: http://ufdc.ufl.edu/UFE0044814.

Council of Science Editors:

Franca RS. Neutron Flux Characterization and Design of Uftr Radiation Beam Port Using Monte Carlo Methods. [Masters Thesis]. University of Florida; 2012. Available from: http://ufdc.ufl.edu/UFE0044814

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