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You searched for subject:(FUEL ELEMENTS FUEL COMPONENTS FUEL RODS NUCLEAR ENGINEERING ). Showing records 1 – 30 of 236920 total matches.

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The Ohio State University

1. Saltos, N. Nicholas. An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays .

Degree: PhD, Graduate School, 1987, The Ohio State University

Subjects/Keywords: Engineering; Nuclear fuel rods; Heat

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

APA (6th Edition):

Saltos, N. N. (1987). An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays . (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1487329662146664

Chicago Manual of Style (16th Edition):

Saltos, N Nicholas. “An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays .” 1987. Doctoral Dissertation, The Ohio State University. Accessed October 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487329662146664.

MLA Handbook (7th Edition):

Saltos, N Nicholas. “An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays .” 1987. Web. 17 Oct 2019.

Vancouver:

Saltos NN. An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays . [Internet] [Doctoral dissertation]. The Ohio State University; 1987. [cited 2019 Oct 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1487329662146664.

Council of Science Editors:

Saltos NN. An efficient variational solution of the transient radial-azimuthal heat transport in nuclear fuel rod arrays . [Doctoral Dissertation]. The Ohio State University; 1987. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1487329662146664


University of California – Berkeley

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

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

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

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

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APA (6th Edition):

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

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

Chicago Manual of Style (16th Edition):

Terrani, Kurt Amir. “Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors.” 2010. Thesis, University of California – Berkeley. Accessed October 17, 2019. http://www.escholarship.org/uc/item/48d78064.

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

MLA Handbook (7th Edition):

Terrani, Kurt Amir. “Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors.” 2010. Web. 17 Oct 2019.

Vancouver:

Terrani KA. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2019 Oct 17]. Available from: http://www.escholarship.org/uc/item/48d78064.

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

Council of Science Editors:

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

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


Texas A&M University

3. Carpenter, David Charles. SP1TFRE-SP-100 transient fuel rod evaluation code.

Degree: MS, nuclear engineering, 2012, Texas A&M University

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Nuclear fuel rods - Thermal properties.; Nuclear fuel elements - Data processing.

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APA (6th Edition):

Carpenter, D. C. (2012). SP1TFRE-SP-100 transient fuel rod evaluation code. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1986-THESIS-C295

Chicago Manual of Style (16th Edition):

Carpenter, David Charles. “SP1TFRE-SP-100 transient fuel rod evaluation code.” 2012. Masters Thesis, Texas A&M University. Accessed October 17, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1986-THESIS-C295.

MLA Handbook (7th Edition):

Carpenter, David Charles. “SP1TFRE-SP-100 transient fuel rod evaluation code.” 2012. Web. 17 Oct 2019.

Vancouver:

Carpenter DC. SP1TFRE-SP-100 transient fuel rod evaluation code. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1986-THESIS-C295.

Council of Science Editors:

Carpenter DC. SP1TFRE-SP-100 transient fuel rod evaluation code. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1986-THESIS-C295


MIT

4. Allen, George Charman. The reactor engineering of the MITR-II construction and startup .

Degree: 1976, MIT

Subjects/Keywords: Nuclear Engineering; Nuclear fuel elements

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APA (6th Edition):

Allen, G. C. (1976). The reactor engineering of the MITR-II construction and startup . (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/27461

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):

Allen, George Charman. “The reactor engineering of the MITR-II construction and startup .” 1976. Thesis, MIT. Accessed October 17, 2019. http://hdl.handle.net/1721.1/27461.

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

MLA Handbook (7th Edition):

Allen, George Charman. “The reactor engineering of the MITR-II construction and startup .” 1976. Web. 17 Oct 2019.

Vancouver:

Allen GC. The reactor engineering of the MITR-II construction and startup . [Internet] [Thesis]. MIT; 1976. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1721.1/27461.

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

Council of Science Editors:

Allen GC. The reactor engineering of the MITR-II construction and startup . [Thesis]. MIT; 1976. Available from: http://hdl.handle.net/1721.1/27461

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


Virginia Tech

5. Southers, Jack Daniel. The F [subscript N] method for a bare critical cylinder.

Degree: MS, Nuclear Science and Engineering, 1982, Virginia Tech

Subjects/Keywords: LD5655.V855 1982.S667; Nuclear fuel rods; Nuclear fuel elements  – Computer programs; Criticality (Nuclear engineering); Neutron transport theory

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APA (6th Edition):

Southers, J. D. (1982). The F [subscript N] method for a bare critical cylinder. (Masters Thesis). Virginia Tech. Retrieved from http://hdl.handle.net/10919/80216

Chicago Manual of Style (16th Edition):

Southers, Jack Daniel. “The F [subscript N] method for a bare critical cylinder.” 1982. Masters Thesis, Virginia Tech. Accessed October 17, 2019. http://hdl.handle.net/10919/80216.

MLA Handbook (7th Edition):

Southers, Jack Daniel. “The F [subscript N] method for a bare critical cylinder.” 1982. Web. 17 Oct 2019.

Vancouver:

Southers JD. The F [subscript N] method for a bare critical cylinder. [Internet] [Masters thesis]. Virginia Tech; 1982. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/10919/80216.

Council of Science Editors:

Southers JD. The F [subscript N] method for a bare critical cylinder. [Masters Thesis]. Virginia Tech; 1982. Available from: http://hdl.handle.net/10919/80216


Texas A&M University

6. Simmons, Jeffrey Warren. An evaluation of thermal modeling techniques utilized for nuclear fuel rods.

Degree: MS, nuclear engineering, 2012, Texas A&M University

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Nuclear fuel rods - Thermal properties.; Nuclear fuel claddings.

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APA (6th Edition):

Simmons, J. W. (2012). An evaluation of thermal modeling techniques utilized for nuclear fuel rods. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-S5915

Chicago Manual of Style (16th Edition):

Simmons, Jeffrey Warren. “An evaluation of thermal modeling techniques utilized for nuclear fuel rods.” 2012. Masters Thesis, Texas A&M University. Accessed October 17, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-S5915.

MLA Handbook (7th Edition):

Simmons, Jeffrey Warren. “An evaluation of thermal modeling techniques utilized for nuclear fuel rods.” 2012. Web. 17 Oct 2019.

Vancouver:

Simmons JW. An evaluation of thermal modeling techniques utilized for nuclear fuel rods. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-S5915.

Council of Science Editors:

Simmons JW. An evaluation of thermal modeling techniques utilized for nuclear fuel rods. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-S5915


Oregon State University

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

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

Subjects/Keywords: Nuclear fuel elements

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Clark, R. G. (Robert Gilder), 1917-2005. “Monitoring surface temperature of irradiated fuel elements.” 1963. Masters Thesis, Oregon State University. Accessed October 17, 2019. http://hdl.handle.net/1957/48787.

MLA Handbook (7th Edition):

Clark, R. G. (Robert Gilder), 1917-2005. “Monitoring surface temperature of irradiated fuel elements.” 1963. Web. 17 Oct 2019.

Vancouver:

Clark, R. G. (Robert Gilder) 1. Monitoring surface temperature of irradiated fuel elements. [Internet] [Masters thesis]. Oregon State University; 1963. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1957/48787.

Council of Science Editors:

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


Oregon State University

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

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Latimer, Griffen D. “Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF.” 2016. Masters Thesis, Oregon State University. Accessed October 17, 2019. http://hdl.handle.net/1957/60099.

MLA Handbook (7th Edition):

Latimer, Griffen D. “Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF.” 2016. Web. 17 Oct 2019.

Vancouver:

Latimer GD. Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1957/60099.

Council of Science Editors:

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


MIT

9. Rivera, John Edward. Performance of light water reactor fuel rods during plant power changes .

Degree: Nuclear Engineering, 1981, MIT

Subjects/Keywords: Nuclear Engineering.; Light water reactors; Nuclear fuel rods; Nuclear fuel claddings; Zircaloy-2

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APA (6th Edition):

Rivera, J. E. (1981). Performance of light water reactor fuel rods during plant power changes . (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/15854

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):

Rivera, John Edward. “Performance of light water reactor fuel rods during plant power changes .” 1981. Thesis, MIT. Accessed October 17, 2019. http://hdl.handle.net/1721.1/15854.

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

MLA Handbook (7th Edition):

Rivera, John Edward. “Performance of light water reactor fuel rods during plant power changes .” 1981. Web. 17 Oct 2019.

Vancouver:

Rivera JE. Performance of light water reactor fuel rods during plant power changes . [Internet] [Thesis]. MIT; 1981. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1721.1/15854.

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

Council of Science Editors:

Rivera JE. Performance of light water reactor fuel rods during plant power changes . [Thesis]. MIT; 1981. Available from: http://hdl.handle.net/1721.1/15854

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


University of Arizona

10. Verdon, Charles Peter, 1951-. Criticality considerations for low enrichment fuel reprocessing .

Degree: 1976, University of Arizona

Subjects/Keywords: Criticality (Nuclear engineering); Nuclear fuel elements.; Solid fuel reactors.

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APA (6th Edition):

Verdon, Charles Peter, 1. (1976). Criticality considerations for low enrichment fuel reprocessing . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/347892

Chicago Manual of Style (16th Edition):

Verdon, Charles Peter, 1951-. “Criticality considerations for low enrichment fuel reprocessing .” 1976. Masters Thesis, University of Arizona. Accessed October 17, 2019. http://hdl.handle.net/10150/347892.

MLA Handbook (7th Edition):

Verdon, Charles Peter, 1951-. “Criticality considerations for low enrichment fuel reprocessing .” 1976. Web. 17 Oct 2019.

Vancouver:

Verdon, Charles Peter 1. Criticality considerations for low enrichment fuel reprocessing . [Internet] [Masters thesis]. University of Arizona; 1976. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/10150/347892.

Council of Science Editors:

Verdon, Charles Peter 1. Criticality considerations for low enrichment fuel reprocessing . [Masters Thesis]. University of Arizona; 1976. Available from: http://hdl.handle.net/10150/347892


Oregon State University

11. Willison, James Stuart. Thermal conductivity modeling of unrestructured sphere pac nuclear fuels.

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

 In order to properly model the temperature distribution of a nuclear fuel pin, the thermal conductivity of the fuel must be known. For sphere pac… (more)

Subjects/Keywords: Nuclear fuel rods  – Thermal properties

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APA (6th Edition):

Willison, J. S. (1981). Thermal conductivity modeling of unrestructured sphere pac nuclear fuels. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41979

Chicago Manual of Style (16th Edition):

Willison, James Stuart. “Thermal conductivity modeling of unrestructured sphere pac nuclear fuels.” 1981. Masters Thesis, Oregon State University. Accessed October 17, 2019. http://hdl.handle.net/1957/41979.

MLA Handbook (7th Edition):

Willison, James Stuart. “Thermal conductivity modeling of unrestructured sphere pac nuclear fuels.” 1981. Web. 17 Oct 2019.

Vancouver:

Willison JS. Thermal conductivity modeling of unrestructured sphere pac nuclear fuels. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1957/41979.

Council of Science Editors:

Willison JS. Thermal conductivity modeling of unrestructured sphere pac nuclear fuels. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/41979


ETH Zürich

12. Chionis, Dionysios. Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K.

Degree: 2014, ETH Zürich

Subjects/Keywords: KERNBRENNSTOFFE + BRENNSTOFFELEMENTE + BRENNSTÄBE (KERNTECHNIK); KERNREAKTORSICHERHEIT (KERNTECHNIK); SICHERHEITSANALYSE (UNFALLVERHÜTUNG); COMPUTERSIMULATION; FUEL ELEMENTS + FUEL COMPONENTS + FUEL RODS (NUCLEAR ENGINEERING); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); SAFETY ANALYSIS (RESCUE ASSISTANCE); COMPUTER SIMULATION; info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/333.7; Natural resources, energy and environment; Natural resources, energy and environment

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APA (6th Edition):

Chionis, D. (2014). Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K. (Thesis). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/154911

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):

Chionis, Dionysios. “Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K.” 2014. Thesis, ETH Zürich. Accessed October 17, 2019. http://hdl.handle.net/20.500.11850/154911.

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

MLA Handbook (7th Edition):

Chionis, Dionysios. “Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K.” 2014. Web. 17 Oct 2019.

Vancouver:

Chionis D. Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K. [Internet] [Thesis]. ETH Zürich; 2014. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/20.500.11850/154911.

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

Council of Science Editors:

Chionis D. Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K. [Thesis]. ETH Zürich; 2014. Available from: http://hdl.handle.net/20.500.11850/154911

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


MIT

13. Meagher, Paul Christopher. Design of central irradiation facilities for the MITR-II research reactor.

Degree: 1977, MIT

Subjects/Keywords: Nuclear Engineering; Nuclear fuel elements; Irradiation

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APA (6th Edition):

Meagher, P. C. (1977). Design of central irradiation facilities for the MITR-II research reactor. (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/79443

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):

Meagher, Paul Christopher. “Design of central irradiation facilities for the MITR-II research reactor. ” 1977. Thesis, MIT. Accessed October 17, 2019. http://hdl.handle.net/1721.1/79443.

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

MLA Handbook (7th Edition):

Meagher, Paul Christopher. “Design of central irradiation facilities for the MITR-II research reactor. ” 1977. Web. 17 Oct 2019.

Vancouver:

Meagher PC. Design of central irradiation facilities for the MITR-II research reactor. [Internet] [Thesis]. MIT; 1977. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1721.1/79443.

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

Council of Science Editors:

Meagher PC. Design of central irradiation facilities for the MITR-II research reactor. [Thesis]. MIT; 1977. Available from: http://hdl.handle.net/1721.1/79443

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


Virginia Commonwealth University

14. 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 October 17, 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. 17 Oct 2019.

Vancouver:

Britton KA. Neutronics Studies on the NIST Reactor Using the GA LEU fuel. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 Oct 17]. 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


ETH Zürich

15. Orlov, Andrey. Corrosion product deposition on fuel element surfaces of a boiling water reactor.

Degree: 2012, ETH Zürich

Subjects/Keywords: SIEDEWASSERREAKTOREN, SWR (KERNTECHNIK); KERNBRENNSTOFFE + BRENNSTOFFELEMENTE + BRENNSTÄBE (KERNTECHNIK); EROSION + KORROSION + VERWITTERUNG (ABLAGERUNGSMILIEU); BOILING-WATER REACTORS, BWR (NUCLEAR ENGINEERING); FUEL ELEMENTS + FUEL COMPONENTS + FUEL RODS (NUCLEAR ENGINEERING); EROSION + CORROSION + WEATHERING (SEDIMENTARY ENVIRONMENT); info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/333.7; Natural resources, energy and environment; Natural resources, energy and environment

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APA (6th Edition):

Orlov, A. (2012). Corrosion product deposition on fuel element surfaces of a boiling water reactor. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/153294

Chicago Manual of Style (16th Edition):

Orlov, Andrey. “Corrosion product deposition on fuel element surfaces of a boiling water reactor.” 2012. Doctoral Dissertation, ETH Zürich. Accessed October 17, 2019. http://hdl.handle.net/20.500.11850/153294.

MLA Handbook (7th Edition):

Orlov, Andrey. “Corrosion product deposition on fuel element surfaces of a boiling water reactor.” 2012. Web. 17 Oct 2019.

Vancouver:

Orlov A. Corrosion product deposition on fuel element surfaces of a boiling water reactor. [Internet] [Doctoral dissertation]. ETH Zürich; 2012. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/20.500.11850/153294.

Council of Science Editors:

Orlov A. Corrosion product deposition on fuel element surfaces of a boiling water reactor. [Doctoral Dissertation]. ETH Zürich; 2012. Available from: http://hdl.handle.net/20.500.11850/153294


MIT

16. Masterson, Robert Edward. Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores.

Degree: 1977, MIT

Subjects/Keywords: Nuclear Engineering; Nuclear fuel elements Thermal properties; Nuclear fuel elements Computer programs

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APA (6th Edition):

Masterson, R. E. (1977). Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/16334

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):

Masterson, Robert Edward. “Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. ” 1977. Thesis, MIT. Accessed October 17, 2019. http://hdl.handle.net/1721.1/16334.

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

MLA Handbook (7th Edition):

Masterson, Robert Edward. “Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. ” 1977. Web. 17 Oct 2019.

Vancouver:

Masterson RE. Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. [Internet] [Thesis]. MIT; 1977. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1721.1/16334.

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

Council of Science Editors:

Masterson RE. Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. [Thesis]. MIT; 1977. Available from: http://hdl.handle.net/1721.1/16334

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


Virginia Commonwealth University

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

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

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

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

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APA (6th Edition):

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

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

Chicago Manual of Style (16th Edition):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Thesis, Virginia Commonwealth University. Accessed October 17, 2019. https://scholarscompass.vcu.edu/etd/5690.

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

MLA Handbook (7th Edition):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Web. 17 Oct 2019.

Vancouver:

Britt TC. Innovative Fuel Design to Improve Proliferation Management. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 Oct 17]. Available from: https://scholarscompass.vcu.edu/etd/5690.

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

Council of Science Editors:

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

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


University of South Carolina

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

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Metzger, Kathryn Elizabeth. “Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method.” 2013. Masters Thesis, University of South Carolina. Accessed October 17, 2019. https://scholarcommons.sc.edu/etd/2368.

MLA Handbook (7th Edition):

Metzger, Kathryn Elizabeth. “Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method.” 2013. Web. 17 Oct 2019.

Vancouver:

Metzger KE. Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method. [Internet] [Masters thesis]. University of South Carolina; 2013. [cited 2019 Oct 17]. Available from: https://scholarcommons.sc.edu/etd/2368.

Council of Science Editors:

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


ETH Zürich

19. Reiterer, Florian. Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method.

Degree: 2011, ETH Zürich

Subjects/Keywords: KERNBRENNSTOFFE + BRENNSTOFFELEMENTE + BRENNSTÄBE (KERNTECHNIK); GAS-FLÜSSIGKEITSGEMISCHE/EMULSIONEN (FLUIDDYNAMIK); TURBULENTE STRÖMUNG (FLUIDDYNAMIK); COMPUTATIONAL FLUID DYNAMICS (FLUIDMECHANIK); FUEL ELEMENTS + FUEL COMPONENTS + FUEL RODS (NUCLEAR ENGINEERING); MIXED-PHASE FLOW, FOAMS AND EMULSIONS (FLUID DYNAMICS); TURBULENT FLOW (FLUID DYNAMICS); COMPUTATIONAL FLUID DYNAMICS (FLUID MECHANICS); info:eu-repo/classification/ddc/333.7; Natural resources, energy and environment

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APA (6th Edition):

Reiterer, F. (2011). Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method. (Thesis). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/153213

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):

Reiterer, Florian. “Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method.” 2011. Thesis, ETH Zürich. Accessed October 17, 2019. http://hdl.handle.net/20.500.11850/153213.

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

MLA Handbook (7th Edition):

Reiterer, Florian. “Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method.” 2011. Web. 17 Oct 2019.

Vancouver:

Reiterer F. Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method. [Internet] [Thesis]. ETH Zürich; 2011. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/20.500.11850/153213.

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

Council of Science Editors:

Reiterer F. Simulation of single-phase mixing in fuel rod-bundles using an immersed boundary method. [Thesis]. ETH Zürich; 2011. Available from: http://hdl.handle.net/20.500.11850/153213

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


University of Michigan

20. Olhoeft, Jack Emil. The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements.

Degree: 1962, University of Michigan

Subjects/Keywords: Nuclear Fuel Elements.; Doppler Effect.; Engineering

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APA (6th Edition):

Olhoeft, J. E. (1962). The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements. (Thesis). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/6891

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):

Olhoeft, Jack Emil. “The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements.” 1962. Thesis, University of Michigan. Accessed October 17, 2019. http://hdl.handle.net/2027.42/6891.

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

MLA Handbook (7th Edition):

Olhoeft, Jack Emil. “The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements.” 1962. Web. 17 Oct 2019.

Vancouver:

Olhoeft JE. The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements. [Internet] [Thesis]. University of Michigan; 1962. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/2027.42/6891.

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

Council of Science Editors:

Olhoeft JE. The Doppler Effect for a non-uniform temperature distribution in reactor fuel elements. [Thesis]. University of Michigan; 1962. Available from: http://hdl.handle.net/2027.42/6891

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


The Ohio State University

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

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Masters Thesis, The Ohio State University. Accessed October 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

MLA Handbook (7th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Web. 17 Oct 2019.

Vancouver:

Yee SK. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Oct 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

Council of Science Editors:

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


Texas A&M University

22. Bechler, Eric Wayne. Evaluation of fuel rod characterization for transient fuel modeling.

Degree: MS, nuclear engineering, 2012, Texas A&M University

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Nuclear fuel rods.; Nuclear fuels - Testing.

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APA (6th Edition):

Bechler, E. W. (2012). Evaluation of fuel rod characterization for transient fuel modeling. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-B391

Chicago Manual of Style (16th Edition):

Bechler, Eric Wayne. “Evaluation of fuel rod characterization for transient fuel modeling.” 2012. Masters Thesis, Texas A&M University. Accessed October 17, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-B391.

MLA Handbook (7th Edition):

Bechler, Eric Wayne. “Evaluation of fuel rod characterization for transient fuel modeling.” 2012. Web. 17 Oct 2019.

Vancouver:

Bechler EW. Evaluation of fuel rod characterization for transient fuel modeling. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-B391.

Council of Science Editors:

Bechler EW. Evaluation of fuel rod characterization for transient fuel modeling. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-B391


University of Arizona

23. Lamkin, David Ernest, 1940-. ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT .

Degree: 1974, University of Arizona

Subjects/Keywords: Nuclear fuel elements  – Mathematical elements.

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APA (6th Edition):

Lamkin, David Ernest, 1. (1974). ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT . (Doctoral Dissertation). University of Arizona. Retrieved from http://hdl.handle.net/10150/288210

Chicago Manual of Style (16th Edition):

Lamkin, David Ernest, 1940-. “ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT .” 1974. Doctoral Dissertation, University of Arizona. Accessed October 17, 2019. http://hdl.handle.net/10150/288210.

MLA Handbook (7th Edition):

Lamkin, David Ernest, 1940-. “ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT .” 1974. Web. 17 Oct 2019.

Vancouver:

Lamkin, David Ernest 1. ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT . [Internet] [Doctoral dissertation]. University of Arizona; 1974. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/10150/288210.

Council of Science Editors:

Lamkin, David Ernest 1. ANALYTICAL STRESS ANALYSIS SOLUTION FOR A SIMPLIFIED MODEL OF A REACTOR FUEL ELEMENT . [Doctoral Dissertation]. University of Arizona; 1974. Available from: http://hdl.handle.net/10150/288210


University of Manchester

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

Degree: 2015, University of Manchester

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

Subjects/Keywords: Nuclear fuel reprocessing

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Tucker, Kate Louise. “Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems.” 2015. Doctoral Dissertation, University of Manchester. Accessed October 17, 2019. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686.

MLA Handbook (7th Edition):

Tucker, Kate Louise. “Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems.” 2015. Web. 17 Oct 2019.

Vancouver:

Tucker KL. Heavy Metal Extraction Using Advanced Liquid - Liquid Style Partitioning Systems. [Internet] [Doctoral dissertation]. University of Manchester; 2015. [cited 2019 Oct 17]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:274686.

Council of Science Editors:

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


University of New Mexico

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

Degree: Nuclear Engineering, 2013, University of New Mexico

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

Subjects/Keywords: nuclear; fuel; diffusion

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Edelmann, Paul. “Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel.” 2013. Doctoral Dissertation, University of New Mexico. Accessed October 17, 2019. http://hdl.handle.net/1928/23107.

MLA Handbook (7th Edition):

Edelmann, Paul. “Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel.” 2013. Web. 17 Oct 2019.

Vancouver:

Edelmann P. Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel. [Internet] [Doctoral dissertation]. University of New Mexico; 2013. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1928/23107.

Council of Science Editors:

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


MIT

26. Da Silva, Othon Luiz Pinheiro. Fuel element performance maps for nuclear reactor operational decisions.

Degree: 1978, MIT

Subjects/Keywords: Nuclear Engineering; Nuclear fuel elements; Pressurized water reactors; Nuclear fuel claddings

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APA (6th Edition):

Da Silva, O. L. P. (1978). Fuel element performance maps for nuclear reactor operational decisions. (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/54904

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):

Da Silva, Othon Luiz Pinheiro. “Fuel element performance maps for nuclear reactor operational decisions. ” 1978. Thesis, MIT. Accessed October 17, 2019. http://hdl.handle.net/1721.1/54904.

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

MLA Handbook (7th Edition):

Da Silva, Othon Luiz Pinheiro. “Fuel element performance maps for nuclear reactor operational decisions. ” 1978. Web. 17 Oct 2019.

Vancouver:

Da Silva OLP. Fuel element performance maps for nuclear reactor operational decisions. [Internet] [Thesis]. MIT; 1978. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1721.1/54904.

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

Council of Science Editors:

Da Silva OLP. Fuel element performance maps for nuclear reactor operational decisions. [Thesis]. MIT; 1978. Available from: http://hdl.handle.net/1721.1/54904

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


Texas A&M University

27. Parthasarathy, Rajalakshmi. Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor.

Degree: MS, nuclear engineering, 2012, Texas A&M University

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Uranium enrichment.; Nuclear fuel rods.

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APA (6th Edition):

Parthasarathy, R. (2012). Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-P273

Chicago Manual of Style (16th Edition):

Parthasarathy, Rajalakshmi. “Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor.” 2012. Masters Thesis, Texas A&M University. Accessed October 17, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-P273.

MLA Handbook (7th Edition):

Parthasarathy, Rajalakshmi. “Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor.” 2012. Web. 17 Oct 2019.

Vancouver:

Parthasarathy R. Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-P273.

Council of Science Editors:

Parthasarathy R. Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-P273


Iowa State University

28. 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 October 17, 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. 17 Oct 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 Oct 17]. 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

29. 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 October 17, 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. 17 Oct 2019.

Vancouver:

McCauley JJ. A review of the MITR-II basis accident . [Internet] [Thesis]. MIT; 1982. [cited 2019 Oct 17]. 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


University of Tennessee – Knoxville

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

Degree: 2016, University of Tennessee – Knoxville

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed October 17, 2019. https://trace.tennessee.edu/utk_graddiss/4156.

MLA Handbook (7th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Web. 17 Oct 2019.

Vancouver:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2019 Oct 17]. Available from: https://trace.tennessee.edu/utk_graddiss/4156.

Council of Science Editors:

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

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