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You searched for subject:(Accident tolerant fuel). Showing records 1 – 12 of 12 total matches.

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McMaster University

1. 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 April 19, 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. 19 Apr 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Apr 19]. 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


University of Tennessee – Knoxville

2. Sweet, Ryan Terrence. Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements.

Degree: 2018, University of Tennessee – Knoxville

 Alternative cladding materials have been proposed to replace the currently used zirconium (Zr)-based alloys, in order to improve the accident tolerance of light water reactor… (more)

Subjects/Keywords: BISON; fuel performance; fuel modeling and simulation; accident tolerant fuels; FeCrAl

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APA (6th Edition):

Sweet, R. T. (2018). Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/5038

Chicago Manual of Style (16th Edition):

Sweet, Ryan Terrence. “Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements.” 2018. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed April 19, 2019. https://trace.tennessee.edu/utk_graddiss/5038.

MLA Handbook (7th Edition):

Sweet, Ryan Terrence. “Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements.” 2018. Web. 19 Apr 2019.

Vancouver:

Sweet RT. Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2018. [cited 2019 Apr 19]. Available from: https://trace.tennessee.edu/utk_graddiss/5038.

Council of Science Editors:

Sweet RT. Thermo-mechanical analysis of iron-chromium-aluminum (FeCrAl) alloy cladding for light water reactor fuel elements. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2018. Available from: https://trace.tennessee.edu/utk_graddiss/5038


University of Florida

3. Ironman, Timothy J. An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets.

Degree: PhD, Nuclear Engineering Sciences - Nuclear and Radiological Engineering, 2017, University of Florida

 The viability of spark plasma sintering (SPS) for fabrication of industrial-grade nuclear fuel pellets is explored by utilizing die designs for single and multiple pellet… (more)

Subjects/Keywords: accident-tolerant-fuel  – advanced-manufacturing  – batch-processing  – commercialization  – nuclear-fuel  – spark-plasma-sintering

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APA (6th Edition):

Ironman, T. J. (2017). An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets. (Doctoral Dissertation). University of Florida. Retrieved from http://ufdc.ufl.edu/UFE0051840

Chicago Manual of Style (16th Edition):

Ironman, Timothy J. “An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets.” 2017. Doctoral Dissertation, University of Florida. Accessed April 19, 2019. http://ufdc.ufl.edu/UFE0051840.

MLA Handbook (7th Edition):

Ironman, Timothy J. “An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets.” 2017. Web. 19 Apr 2019.

Vancouver:

Ironman TJ. An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets. [Internet] [Doctoral dissertation]. University of Florida; 2017. [cited 2019 Apr 19]. Available from: http://ufdc.ufl.edu/UFE0051840.

Council of Science Editors:

Ironman TJ. An Exploration of the Viability of Spark Plasma Sintering for the Commercial Fabrication of Nuclear Fuel Pellets. [Doctoral Dissertation]. University of Florida; 2017. Available from: http://ufdc.ufl.edu/UFE0051840


Penn State University

4. Younker, Ian Mark. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.

Degree: MS, Nuclear Engineering, 2015, Penn State University

Accident tolerant fuels (ATF) are designed to mitigate the detrimental interaction between zirconium-alloy cladding and high temperature steam found during beyond design basis accident conditions.… (more)

Subjects/Keywords: Light water reactors; Accident Tolerant Fuel; Ceramic coatings for clad; Alternative clad

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APA (6th Edition):

Younker, I. M. (2015). Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/25009

Chicago Manual of Style (16th Edition):

Younker, Ian Mark. “Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.” 2015. Masters Thesis, Penn State University. Accessed April 19, 2019. https://etda.libraries.psu.edu/catalog/25009.

MLA Handbook (7th Edition):

Younker, Ian Mark. “Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.” 2015. Web. 19 Apr 2019.

Vancouver:

Younker IM. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. [Internet] [Masters thesis]. Penn State University; 2015. [cited 2019 Apr 19]. Available from: https://etda.libraries.psu.edu/catalog/25009.

Council of Science Editors:

Younker IM. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. [Masters Thesis]. Penn State University; 2015. Available from: https://etda.libraries.psu.edu/catalog/25009


University of South Carolina

5. Li, Bo-Shiuan. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.

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

  Ceramic materials such as silicon carbide (SiC) are promising candidate materials for nuclear fuel cladding and are of interest as part of a potential… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Accident tolerant fuel; ceramic cladding; FRAPCON; Fuel performance code; Pellet cladding mechanical interactions; Silicon carbide

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APA (6th Edition):

Li, B. (2013). Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/2366

Chicago Manual of Style (16th Edition):

Li, Bo-Shiuan. “Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.” 2013. Masters Thesis, University of South Carolina. Accessed April 19, 2019. https://scholarcommons.sc.edu/etd/2366.

MLA Handbook (7th Edition):

Li, Bo-Shiuan. “Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions.” 2013. Web. 19 Apr 2019.

Vancouver:

Li B. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. [Internet] [Masters thesis]. University of South Carolina; 2013. [cited 2019 Apr 19]. Available from: https://scholarcommons.sc.edu/etd/2366.

Council of Science Editors:

Li B. Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions. [Masters Thesis]. University of South Carolina; 2013. Available from: https://scholarcommons.sc.edu/etd/2366


Virginia Commonwealth University

6. Morgan, Andrew. JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS.

Degree: MS, Mechanical and Nuclear Engineering, 2014, Virginia Commonwealth University

  Silicon Carbide (SiC) is increasingly gaining attention as a potential fuel cladding material, on account of its favorable thermo-mechanical and neutronic properties. The major… (more)

Subjects/Keywords: Silicon Carbide; SiC; FeCrAl; Hermetic Sealing; Accident Tolerant Fuels; ATF; Nuclear Fuel Cladding; Materials Science and Engineering

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APA (6th Edition):

Morgan, A. (2014). JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS. (Thesis). Virginia Commonwealth University. Retrieved from https://scholarscompass.vcu.edu/etd/3529

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):

Morgan, Andrew. “JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS.” 2014. Thesis, Virginia Commonwealth University. Accessed April 19, 2019. https://scholarscompass.vcu.edu/etd/3529.

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

MLA Handbook (7th Edition):

Morgan, Andrew. “JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS.” 2014. Web. 19 Apr 2019.

Vancouver:

Morgan A. JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS. [Internet] [Thesis]. Virginia Commonwealth University; 2014. [cited 2019 Apr 19]. Available from: https://scholarscompass.vcu.edu/etd/3529.

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

Council of Science Editors:

Morgan A. JOINING AND HERMETIC SEALING OF SILICON CARBIDE USING IRON, CHROMIUM, AND ALUMINUM ALLOYS. [Thesis]. Virginia Commonwealth University; 2014. Available from: https://scholarscompass.vcu.edu/etd/3529

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


University of Manchester

7. Buckley, James. The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance.

Degree: PhD, 2017, University of Manchester

Fuel for nuclear reactors with an increased thermal conductivity offers the potential for lower fuel operating temperatures and reduced fission gas release rates. Uranium dioxide… (more)

Subjects/Keywords: sintering; Energy; Spark plasma sintering; Nuetronics; Accident Tolerant Fuel; Uranium dioxide; Silicon carbide; Molybdenum; NFCE; Thermal conductivity

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APA (6th Edition):

Buckley, J. (2017). The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/the-manufacture-and-characterisation-of-composite-nuclear-fuel-for-improved-inreactor-performance(b5ea0339-7c5b-46d2-a696-743007b9e94b).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.728015

Chicago Manual of Style (16th Edition):

Buckley, James. “The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance.” 2017. Doctoral Dissertation, University of Manchester. Accessed April 19, 2019. https://www.research.manchester.ac.uk/portal/en/theses/the-manufacture-and-characterisation-of-composite-nuclear-fuel-for-improved-inreactor-performance(b5ea0339-7c5b-46d2-a696-743007b9e94b).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.728015.

MLA Handbook (7th Edition):

Buckley, James. “The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance.” 2017. Web. 19 Apr 2019.

Vancouver:

Buckley J. The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance. [Internet] [Doctoral dissertation]. University of Manchester; 2017. [cited 2019 Apr 19]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-manufacture-and-characterisation-of-composite-nuclear-fuel-for-improved-inreactor-performance(b5ea0339-7c5b-46d2-a696-743007b9e94b).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.728015.

Council of Science Editors:

Buckley J. The manufacture and characterisation of composite nuclear fuel for improved in-reactor performance. [Doctoral Dissertation]. University of Manchester; 2017. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-manufacture-and-characterisation-of-composite-nuclear-fuel-for-improved-inreactor-performance(b5ea0339-7c5b-46d2-a696-743007b9e94b).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.728015


University of Manchester

8. Buckley, James. The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance.

Degree: 2017, University of Manchester

Fuel for nuclear reactors with an increased thermal conductivity offers the potential for lower fuel operating temperatures and reduced fission gas release rates. Uranium dioxide… (more)

Subjects/Keywords: Accident Tolerant Fuel; Molybdenum; Silicon carbide; Uranium dioxide; Thermal conductivity; Nuetronics; Energy; Spark plasma sintering; sintering; NFCE

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APA (6th Edition):

Buckley, J. (2017). The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:308287

Chicago Manual of Style (16th Edition):

Buckley, James. “The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance.” 2017. Doctoral Dissertation, University of Manchester. Accessed April 19, 2019. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:308287.

MLA Handbook (7th Edition):

Buckley, James. “The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance.” 2017. Web. 19 Apr 2019.

Vancouver:

Buckley J. The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance. [Internet] [Doctoral dissertation]. University of Manchester; 2017. [cited 2019 Apr 19]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:308287.

Council of Science Editors:

Buckley J. The Manufacture and Characterisation of Composite Nuclear Fuel for Improved In-reactor Performance. [Doctoral Dissertation]. University of Manchester; 2017. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:308287

9. Shapiro, Rachel Ann. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.

Degree: MS, Nuclear Engineering, 2014, Penn State University

 Fully ceramic microencapsulated (FCM) fuel is an accident tolerant design that takes advantage of TRISO technology, embedding the particles in a ceramic matrix (SiC) to… (more)

Subjects/Keywords: PWR; TRISO; accident-tolerant fuel; fully ceramic microencapsulated fuel; neutronics

…of a beyond design basis loss of cooling accident (LOCA), fuel may be uncovered… …characteristics during beyond design basis accident conditions. These new fuel concepts are referred to… …as “accident tolerant fuels” (ATF) and are expected to provide enhanced… …The use of silicon carbide as a clad material is being considered for many accident tolerant… …FCM fuel during a reactivity initiated accident (RIA) transient such as a rod… 

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APA (6th Edition):

Shapiro, R. A. (2014). Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/22708

Chicago Manual of Style (16th Edition):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Masters Thesis, Penn State University. Accessed April 19, 2019. https://etda.libraries.psu.edu/catalog/22708.

MLA Handbook (7th Edition):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Web. 19 Apr 2019.

Vancouver:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Internet] [Masters thesis]. Penn State University; 2014. [cited 2019 Apr 19]. Available from: https://etda.libraries.psu.edu/catalog/22708.

Council of Science Editors:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Masters Thesis]. Penn State University; 2014. Available from: https://etda.libraries.psu.edu/catalog/22708

10. Marquez, Matias G. Silicide fuel swelling behavior and its performance in I2S-LWR.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The swelling mechanisms of U3Si2 under neutron irradiation in reactor conditions are not unequivocally known. The limited experimental evidence that is available suggests that the… (more)

Subjects/Keywords: Silicide fuels; Swelling; Recrystallization; Grain subdivision; Nuclear fuel; Accident tolerant fuel; Advanced fuels; Rim effect; High burnup structure; Fuel performance

…computational codes, that model allows the evaluation of the total swelling of a fuel pellet in a… …reactor environment over the fuel lifetime. Because of the scarcity, or even nearly total… …results in the fuel performance and Chapter 10 contains the conclusion. xi CHAPTER 1… …primarily as heat within the fuel, with a small fraction carried by neutrons and gamma radiation… …the nuclear fuel and its design to the functioning of a nuclear reactor. In particular… 

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APA (6th Edition):

Marquez, M. G. (2015). Silicide fuel swelling behavior and its performance in I2S-LWR. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53970

Chicago Manual of Style (16th Edition):

Marquez, Matias G. “Silicide fuel swelling behavior and its performance in I2S-LWR.” 2015. Masters Thesis, Georgia Tech. Accessed April 19, 2019. http://hdl.handle.net/1853/53970.

MLA Handbook (7th Edition):

Marquez, Matias G. “Silicide fuel swelling behavior and its performance in I2S-LWR.” 2015. Web. 19 Apr 2019.

Vancouver:

Marquez MG. Silicide fuel swelling behavior and its performance in I2S-LWR. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 19]. Available from: http://hdl.handle.net/1853/53970.

Council of Science Editors:

Marquez MG. Silicide fuel swelling behavior and its performance in I2S-LWR. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/53970

11. Stewart, Ian Robert. Impact of Fuel Rod Coatings on Reactor Performance and Safety.

Degree: MS, Nuclear Engineering, 2015, University of Tennessee – Knoxville

  This study evaluates the use of a ceramic coating on the Zr-alloy cladding within a PWR using four ceramic compounds of 5 and 10… (more)

Subjects/Keywords: nuclear engineering; nuclear fuel; accident tolerant fuel; ceramic film; ceramic coating on clad; Ceramic Materials; Engineering; Engineering Science and Materials; Materials Science and Engineering; Nuclear Engineering

Accident Fuel Campaign and have been given the name Accident Tolerant Fuels (ATF) by… …From the lessons learned from the Fukushima Dai-ichi accident, alternative fuel and cladding… …List of Figures Figure 1: Five categories that require consideration for new fuel designs… …2 Figure 2: Fuel geometry used in obtaining PMF… …for thermal resistance across a cylindrical fuel pin .............. 11 Figure 7: Moody… 

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APA (6th Edition):

Stewart, I. R. (2015). Impact of Fuel Rod Coatings on Reactor Performance and Safety. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/3411

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):

Stewart, Ian Robert. “Impact of Fuel Rod Coatings on Reactor Performance and Safety.” 2015. Thesis, University of Tennessee – Knoxville. Accessed April 19, 2019. https://trace.tennessee.edu/utk_gradthes/3411.

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

MLA Handbook (7th Edition):

Stewart, Ian Robert. “Impact of Fuel Rod Coatings on Reactor Performance and Safety.” 2015. Web. 19 Apr 2019.

Vancouver:

Stewart IR. Impact of Fuel Rod Coatings on Reactor Performance and Safety. [Internet] [Thesis]. University of Tennessee – Knoxville; 2015. [cited 2019 Apr 19]. Available from: https://trace.tennessee.edu/utk_gradthes/3411.

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

Council of Science Editors:

Stewart IR. Impact of Fuel Rod Coatings on Reactor Performance and Safety. [Thesis]. University of Tennessee – Knoxville; 2015. Available from: https://trace.tennessee.edu/utk_gradthes/3411

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


Penn State University

12. Alat, Ece. CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE.

Degree: 2018, Penn State University

 This research is focused on developing nuclear fuel claddings with ceramic coatings that can perform well during normal operation and can withstand transient conditions such… (more)

Subjects/Keywords: Accident tolerant fuel; corrosion resistance; oxidation resistance; ceramic coatings; nuclear fuel cladding; titanium aluminum nitride (TiAlN); titanium nitride (TiN); cathodic arc physical vapor deposition; substrate bias; cathode composition; titanium bond coating; substrate surface preparation method; substrate surface roughness; nitrogen partial pressure; coating deposition time; scratch testing; neutronic analysis; multilayer ceramic coatings; air oxidation; supercritical water testing (SCW); X-ray diffraction (XRD); scanning electron microscopy (SEM); Raman spectroscopy; energy dispersive spectroscopy (EDS); differential scanning calorimetry (DSC); thermogravimetric analysis (TGA); autoclave testing

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APA (6th Edition):

Alat, E. (2018). CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE. (Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/15347exa179

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):

Alat, Ece. “CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE.” 2018. Thesis, Penn State University. Accessed April 19, 2019. https://etda.libraries.psu.edu/catalog/15347exa179.

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

MLA Handbook (7th Edition):

Alat, Ece. “CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE.” 2018. Web. 19 Apr 2019.

Vancouver:

Alat E. CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE. [Internet] [Thesis]. Penn State University; 2018. [cited 2019 Apr 19]. Available from: https://etda.libraries.psu.edu/catalog/15347exa179.

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

Council of Science Editors:

Alat E. CERAMIC COATINGS FOR NUCLEAR FUEL CLADDING TO ENHANCE ACCIDENT TOLERANCE. [Thesis]. Penn State University; 2018. Available from: https://etda.libraries.psu.edu/catalog/15347exa179

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

.