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You searched for subject:(Nuclear fuels). Showing records 1 – 30 of 141 total matches.

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Oregon State University

1. Reardon, Patrick Thomas. A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels.

Degree: MS, Nuclear Engineering, 1983, Oregon State University

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Reardon, P. T. (1983). A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41793

Chicago Manual of Style (16th Edition):

Reardon, Patrick Thomas. “A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels.” 1983. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/41793.

MLA Handbook (7th Edition):

Reardon, Patrick Thomas. “A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels.” 1983. Web. 25 Apr 2019.

Vancouver:

Reardon PT. A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels. [Internet] [Masters thesis]. Oregon State University; 1983. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/41793.

Council of Science Editors:

Reardon PT. A two-dimensional analysis of porosity effects on the thermal conductivity of ceramic nuclear fuels. [Masters Thesis]. Oregon State University; 1983. Available from: http://hdl.handle.net/1957/41793


Oregon State University

2. Jenks, Richard P. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel.

Degree: MS, Nuclear Engineering, 1982, Oregon State University

 The design, development, and utilization of a direct shear test apparatus is presented in this thesis. The effectiveness of the device for determining the friction… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Jenks, R. P. (1982). Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41755

Chicago Manual of Style (16th Edition):

Jenks, Richard P. “Direct shear testing of UO₂ sphere-pac nuclear reactor fuel.” 1982. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/41755.

MLA Handbook (7th Edition):

Jenks, Richard P. “Direct shear testing of UO₂ sphere-pac nuclear reactor fuel.” 1982. Web. 25 Apr 2019.

Vancouver:

Jenks RP. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/41755.

Council of Science Editors:

Jenks RP. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. [Masters Thesis]. Oregon State University; 1982. Available from: http://hdl.handle.net/1957/41755


Oregon State University

3. Montgomery, Scott D. Thermal and mechanical behavior of sphere pac fuel.

Degree: MS, Nuclear Engineering, 1982, Oregon State University

 The use of advanced concepts can make the nuclear fuel cycle more efficient by allowing pins to be operated at high powers and to higher… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Montgomery, S. D. (1982). Thermal and mechanical behavior of sphere pac fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41981

Chicago Manual of Style (16th Edition):

Montgomery, Scott D. “Thermal and mechanical behavior of sphere pac fuel.” 1982. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/41981.

MLA Handbook (7th Edition):

Montgomery, Scott D. “Thermal and mechanical behavior of sphere pac fuel.” 1982. Web. 25 Apr 2019.

Vancouver:

Montgomery SD. Thermal and mechanical behavior of sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/41981.

Council of Science Editors:

Montgomery SD. Thermal and mechanical behavior of sphere pac fuel. [Masters Thesis]. Oregon State University; 1982. Available from: http://hdl.handle.net/1957/41981


Oregon State University

4. Henke, Robert K. Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels.

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

 The establishment of any thermal model of reactor fuel requires a thorough understanding of the behavior of the thermal conductivity. This is especially true in… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Henke, R. K. (1981). Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42199

Chicago Manual of Style (16th Edition):

Henke, Robert K. “Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels.” 1981. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/42199.

MLA Handbook (7th Edition):

Henke, Robert K. “Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels.” 1981. Web. 25 Apr 2019.

Vancouver:

Henke RK. Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/42199.

Council of Science Editors:

Henke RK. Stochastic simulation of sphere beds and the effect of packing density on the thermal conductivity of sphere pac nuclear fuels. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/42199


Oregon State University

5. Nielsen, Larry H. An assessment of describing function methods applied to reactor fuel performance analysis.

Degree: MS, Nuclear Engineering, 1980, Oregon State University

 Large digital computer reactor fuel performance codes perform repeated calculations of temperature profiles during transients. The thermal response is required to calculate the mechanical behavior.… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Nielsen, L. H. (1980). An assessment of describing function methods applied to reactor fuel performance analysis. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42808

Chicago Manual of Style (16th Edition):

Nielsen, Larry H. “An assessment of describing function methods applied to reactor fuel performance analysis.” 1980. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/42808.

MLA Handbook (7th Edition):

Nielsen, Larry H. “An assessment of describing function methods applied to reactor fuel performance analysis.” 1980. Web. 25 Apr 2019.

Vancouver:

Nielsen LH. An assessment of describing function methods applied to reactor fuel performance analysis. [Internet] [Masters thesis]. Oregon State University; 1980. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/42808.

Council of Science Editors:

Nielsen LH. An assessment of describing function methods applied to reactor fuel performance analysis. [Masters Thesis]. Oregon State University; 1980. Available from: http://hdl.handle.net/1957/42808


Oregon State University

6. Baker, Ronald Blair. Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel.

Degree: MS, Mechanical Engineering, 1976, Oregon State University

 This report presents a refined method for the calculation of fuel centerline temperatures and the linear-heat-rating-to-incipient melting, ' Q'[subscript m], of mixed-oxide fuel typical of… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Baker, R. B. (1976). Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/43628

Chicago Manual of Style (16th Edition):

Baker, Ronald Blair. “Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel.” 1976. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/43628.

MLA Handbook (7th Edition):

Baker, Ronald Blair. “Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel.” 1976. Web. 25 Apr 2019.

Vancouver:

Baker RB. Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel. [Internet] [Masters thesis]. Oregon State University; 1976. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/43628.

Council of Science Editors:

Baker RB. Modeling the thermal effects of fabricated fuel-to-cladding gap in fast reactor fuel. [Masters Thesis]. Oregon State University; 1976. Available from: http://hdl.handle.net/1957/43628


Oregon State University

7. Alberti, Anthony L. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.

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

 With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption… (more)

Subjects/Keywords: TREAT; Nuclear fuels  – Testing

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APA (6th Edition):

Alberti, A. L. (2015). Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/58315

Chicago Manual of Style (16th Edition):

Alberti, Anthony L. “Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.” 2015. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/58315.

MLA Handbook (7th Edition):

Alberti, Anthony L. “Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility.” 2015. Web. 25 Apr 2019.

Vancouver:

Alberti AL. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/58315.

Council of Science Editors:

Alberti AL. Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. [Masters Thesis]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/58315


Oregon State University

8. Wen, Xianfei. An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel.

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

 High-energy delayed γ-rays from photofission were demonstrated to be signatures for detection and identification of special nuclear materials. Such γ-rays were measured in between linac… (more)

Subjects/Keywords: Photofission; Nuclear fuels  – Analysis

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APA (6th Edition):

Wen, X. (2016). An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/58469

Chicago Manual of Style (16th Edition):

Wen, Xianfei. “An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel.” 2016. Doctoral Dissertation, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/58469.

MLA Handbook (7th Edition):

Wen, Xianfei. “An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel.” 2016. Web. 25 Apr 2019.

Vancouver:

Wen X. An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel. [Internet] [Doctoral dissertation]. Oregon State University; 2016. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/58469.

Council of Science Editors:

Wen X. An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel. [Doctoral Dissertation]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/58469


Oregon State University

9. Bailey, Wendell Jack. Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR).

Degree: MS, Mechanical Engineering, 1960, Oregon State University

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Bailey, W. J. (1960). Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR). (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/50363

Chicago Manual of Style (16th Edition):

Bailey, Wendell Jack. “Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR).” 1960. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/50363.

MLA Handbook (7th Edition):

Bailey, Wendell Jack. “Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR).” 1960. Web. 25 Apr 2019.

Vancouver:

Bailey WJ. Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR). [Internet] [Masters thesis]. Oregon State University; 1960. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/50363.

Council of Science Editors:

Bailey WJ. Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR). [Masters Thesis]. Oregon State University; 1960. Available from: http://hdl.handle.net/1957/50363


Oregon State University

10. Stout, Richard Bartholomew. Optimization of in-core nuclear fuel management in a pressurized water reactor.

Degree: PhD, Mechanical and Nuclear Engineering, 1972, Oregon State University

 Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and… (more)

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Stout, R. B. (1972). Optimization of in-core nuclear fuel management in a pressurized water reactor. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/44778

Chicago Manual of Style (16th Edition):

Stout, Richard Bartholomew. “Optimization of in-core nuclear fuel management in a pressurized water reactor.” 1972. Doctoral Dissertation, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/44778.

MLA Handbook (7th Edition):

Stout, Richard Bartholomew. “Optimization of in-core nuclear fuel management in a pressurized water reactor.” 1972. Web. 25 Apr 2019.

Vancouver:

Stout RB. Optimization of in-core nuclear fuel management in a pressurized water reactor. [Internet] [Doctoral dissertation]. Oregon State University; 1972. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/44778.

Council of Science Editors:

Stout RB. Optimization of in-core nuclear fuel management in a pressurized water reactor. [Doctoral Dissertation]. Oregon State University; 1972. Available from: http://hdl.handle.net/1957/44778


Oregon State University

11. Guenther, Richard John. The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel.

Degree: MS, Nuclear Engineering, 1978, Oregon State University

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Guenther, R. J. (1978). The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42739

Chicago Manual of Style (16th Edition):

Guenther, Richard John. “The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel.” 1978. Masters Thesis, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/42739.

MLA Handbook (7th Edition):

Guenther, Richard John. “The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel.” 1978. Web. 25 Apr 2019.

Vancouver:

Guenther RJ. The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel. [Internet] [Masters thesis]. Oregon State University; 1978. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/42739.

Council of Science Editors:

Guenther RJ. The applicability of sintering mechanisms in the initial stage restructuring and preferential pore migration of irradiated (U₀.₈₅Pu₀.₁₅)C sphere-pac fuel. [Masters Thesis]. Oregon State University; 1978. Available from: http://hdl.handle.net/1957/42739


Kansas State University

12. Giefer, David L. The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system.

Degree: 1974, Kansas State University

Subjects/Keywords: Nuclear fuels

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APA (6th Edition):

Giefer, D. L. (1974). The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system. (Thesis). Kansas State University. Retrieved from http://hdl.handle.net/2097/10983

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):

Giefer, David L. “The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system.” 1974. Thesis, Kansas State University. Accessed April 25, 2019. http://hdl.handle.net/2097/10983.

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

MLA Handbook (7th Edition):

Giefer, David L. “The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system.” 1974. Web. 25 Apr 2019.

Vancouver:

Giefer DL. The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system. [Internet] [Thesis]. Kansas State University; 1974. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/2097/10983.

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

Council of Science Editors:

Giefer DL. The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system. [Thesis]. Kansas State University; 1974. Available from: http://hdl.handle.net/2097/10983

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


Tartu University

13. Auzans, Aris. Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization .

Degree: 2018, Tartu University

 Paljud riigid püüavad piirata kasvuhoonegaaside heitkoguseid ja püüavad keskenduda süsinikuvabadele energiaallikatele, mistõttu on tuumaenergia jätkuva arutelu teema, et laiendada kogu maailma energiatootmise segmenti ja katta… (more)

Subjects/Keywords: nuclear fuels; natural uranium fuels; nuclear technology; nuclear power energetics; economic models

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APA (6th Edition):

Auzans, A. (2018). Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization . (Thesis). Tartu University. Retrieved from http://hdl.handle.net/10062/59904

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):

Auzans, Aris. “Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization .” 2018. Thesis, Tartu University. Accessed April 25, 2019. http://hdl.handle.net/10062/59904.

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

MLA Handbook (7th Edition):

Auzans, Aris. “Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization .” 2018. Web. 25 Apr 2019.

Vancouver:

Auzans A. Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization . [Internet] [Thesis]. Tartu University; 2018. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/10062/59904.

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

Council of Science Editors:

Auzans A. Development of computational model for nuclear energy systems analysis: natural resources optimisation and radiological impact minimization . [Thesis]. Tartu University; 2018. Available from: http://hdl.handle.net/10062/59904

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


Oregon State University

14. Azarfar, Mohammad Ali. A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication.

Degree: PhD, Nuclear Engineering, 1982, Oregon State University

 This study focuses on the development of a methodology to evaluate safeguardability of various processes in the nuclear fuel cycle. National and international implementation of… (more)

Subjects/Keywords: Nuclear fuels  – Methodology

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APA (6th Edition):

Azarfar, M. A. (1982). A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/41719

Chicago Manual of Style (16th Edition):

Azarfar, Mohammad Ali. “A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication.” 1982. Doctoral Dissertation, Oregon State University. Accessed April 25, 2019. http://hdl.handle.net/1957/41719.

MLA Handbook (7th Edition):

Azarfar, Mohammad Ali. “A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication.” 1982. Web. 25 Apr 2019.

Vancouver:

Azarfar MA. A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication. [Internet] [Doctoral dissertation]. Oregon State University; 1982. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/1957/41719.

Council of Science Editors:

Azarfar MA. A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication. [Doctoral Dissertation]. Oregon State University; 1982. Available from: http://hdl.handle.net/1957/41719


The Ohio State University

15. Henderson, Ronald R. A nuclear reactor performance and fuel management simulator for power system planning activities.

Degree: PhD, Graduate School, 1971, The Ohio State University

Subjects/Keywords: Engineering; Nuclear fuels; Nuclear reactors

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APA (6th Edition):

Henderson, R. R. (1971). A nuclear reactor performance and fuel management simulator for power system planning activities. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1486727662648603

Chicago Manual of Style (16th Edition):

Henderson, Ronald R. “A nuclear reactor performance and fuel management simulator for power system planning activities.” 1971. Doctoral Dissertation, The Ohio State University. Accessed April 25, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1486727662648603.

MLA Handbook (7th Edition):

Henderson, Ronald R. “A nuclear reactor performance and fuel management simulator for power system planning activities.” 1971. Web. 25 Apr 2019.

Vancouver:

Henderson RR. A nuclear reactor performance and fuel management simulator for power system planning activities. [Internet] [Doctoral dissertation]. The Ohio State University; 1971. [cited 2019 Apr 25]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486727662648603.

Council of Science Editors:

Henderson RR. A nuclear reactor performance and fuel management simulator for power system planning activities. [Doctoral Dissertation]. The Ohio State University; 1971. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486727662648603


University of Texas – Austin

16. Matavosian, Robert. Complex problems arising in the collision probability theory for neutron transport.

Degree: Mechanical Engineering, 2007, University of Texas – Austin

 Several comprehensive but time consuming neutronic codes are available for performing nuclear reactor and fuel cycle evaluations. In addition, simple models utilizing collision probability theory… (more)

Subjects/Keywords: Nuclear reactors; Nuclear fuels

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APA (6th Edition):

Matavosian, R. (2007). Complex problems arising in the collision probability theory for neutron transport. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/3789

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):

Matavosian, Robert. “Complex problems arising in the collision probability theory for neutron transport.” 2007. Thesis, University of Texas – Austin. Accessed April 25, 2019. http://hdl.handle.net/2152/3789.

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

MLA Handbook (7th Edition):

Matavosian, Robert. “Complex problems arising in the collision probability theory for neutron transport.” 2007. Web. 25 Apr 2019.

Vancouver:

Matavosian R. Complex problems arising in the collision probability theory for neutron transport. [Internet] [Thesis]. University of Texas – Austin; 2007. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/2152/3789.

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

Council of Science Editors:

Matavosian R. Complex problems arising in the collision probability theory for neutron transport. [Thesis]. University of Texas – Austin; 2007. Available from: http://hdl.handle.net/2152/3789

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


University of Arizona

17. Smith, Adrienne Bobbette, 1960-. Nuclear excursions in aqueous solutions of fissile materials .

Degree: 1989, University of Arizona

 Fissile materials in the form of aqueous homogeneous solutions are used during the chemical processing of nuclear materials. In this form there exists the possibility… (more)

Subjects/Keywords: Nuclear fuels.; Nuclear reactor accidents

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APA (6th Edition):

Smith, Adrienne Bobbette, 1. (1989). Nuclear excursions in aqueous solutions of fissile materials . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/277150

Chicago Manual of Style (16th Edition):

Smith, Adrienne Bobbette, 1960-. “Nuclear excursions in aqueous solutions of fissile materials .” 1989. Masters Thesis, University of Arizona. Accessed April 25, 2019. http://hdl.handle.net/10150/277150.

MLA Handbook (7th Edition):

Smith, Adrienne Bobbette, 1960-. “Nuclear excursions in aqueous solutions of fissile materials .” 1989. Web. 25 Apr 2019.

Vancouver:

Smith, Adrienne Bobbette 1. Nuclear excursions in aqueous solutions of fissile materials . [Internet] [Masters thesis]. University of Arizona; 1989. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/10150/277150.

Council of Science Editors:

Smith, Adrienne Bobbette 1. Nuclear excursions in aqueous solutions of fissile materials . [Masters Thesis]. University of Arizona; 1989. Available from: http://hdl.handle.net/10150/277150


The Ohio State University

18. Walters, M. Audeen. Transition from uranium to denatured uranium/thorium fuel in an existing PWR.

Degree: PhD, Graduate School, 1982, The Ohio State University

Subjects/Keywords: Engineering; Uranium; Thorium; Nuclear fuels

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APA (6th Edition):

Walters, M. A. (1982). Transition from uranium to denatured uranium/thorium fuel in an existing PWR. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1487175662514416

Chicago Manual of Style (16th Edition):

Walters, M Audeen. “Transition from uranium to denatured uranium/thorium fuel in an existing PWR.” 1982. Doctoral Dissertation, The Ohio State University. Accessed April 25, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487175662514416.

MLA Handbook (7th Edition):

Walters, M Audeen. “Transition from uranium to denatured uranium/thorium fuel in an existing PWR.” 1982. Web. 25 Apr 2019.

Vancouver:

Walters MA. Transition from uranium to denatured uranium/thorium fuel in an existing PWR. [Internet] [Doctoral dissertation]. The Ohio State University; 1982. [cited 2019 Apr 25]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1487175662514416.

Council of Science Editors:

Walters MA. Transition from uranium to denatured uranium/thorium fuel in an existing PWR. [Doctoral Dissertation]. The Ohio State University; 1982. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1487175662514416


University of Arizona

19. Friedlander, Michael Arthur. AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT.

Degree: 1984, University of Arizona

Subjects/Keywords: Nuclear fuels  – Analysis.; Transfer functions.

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APA (6th Edition):

Friedlander, M. A. (1984). AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT. (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/275098

Chicago Manual of Style (16th Edition):

Friedlander, Michael Arthur. “AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT. ” 1984. Masters Thesis, University of Arizona. Accessed April 25, 2019. http://hdl.handle.net/10150/275098.

MLA Handbook (7th Edition):

Friedlander, Michael Arthur. “AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT. ” 1984. Web. 25 Apr 2019.

Vancouver:

Friedlander MA. AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT. [Internet] [Masters thesis]. University of Arizona; 1984. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/10150/275098.

Council of Science Editors:

Friedlander MA. AN EXPERIMENTAL ANALYSIS OF THE FISSILE CONTENT OF THE TRIGA CORE BY TRANSFER FUNCTION MEASUREMENT. [Masters Thesis]. University of Arizona; 1984. Available from: http://hdl.handle.net/10150/275098


University of Bath

20. Ayling, Joanna R. Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples.

Degree: PhD, 1996, University of Bath

Subjects/Keywords: 621.484; Nuclear fuels; Thermal behaviour

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APA (6th Edition):

Ayling, J. R. (1996). Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples. (Doctoral Dissertation). University of Bath. Retrieved from https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.320437

Chicago Manual of Style (16th Edition):

Ayling, Joanna R. “Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples.” 1996. Doctoral Dissertation, University of Bath. Accessed April 25, 2019. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.320437.

MLA Handbook (7th Edition):

Ayling, Joanna R. “Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples.” 1996. Web. 25 Apr 2019.

Vancouver:

Ayling JR. Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples. [Internet] [Doctoral dissertation]. University of Bath; 1996. [cited 2019 Apr 25]. Available from: https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.320437.

Council of Science Editors:

Ayling JR. Evaluation of a technique for the remote measurement of surface temperature distributions in laser heated samples. [Doctoral Dissertation]. University of Bath; 1996. Available from: https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.320437


University of New South Wales

21. May, James Richard. Studies of high temperature refractory fuels.

Degree: Nuclear Engineering, 1960, University of New South Wales

Subjects/Keywords: Nuclear fuels; Thesis Digitisation Program

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APA (6th Edition):

May, J. R. (1960). Studies of high temperature refractory fuels. (Masters Thesis). University of New South Wales. Retrieved from http://handle.unsw.edu.au/1959.4/57170 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:42749/SOURCE02?view=true

Chicago Manual of Style (16th Edition):

May, James Richard. “Studies of high temperature refractory fuels.” 1960. Masters Thesis, University of New South Wales. Accessed April 25, 2019. http://handle.unsw.edu.au/1959.4/57170 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:42749/SOURCE02?view=true.

MLA Handbook (7th Edition):

May, James Richard. “Studies of high temperature refractory fuels.” 1960. Web. 25 Apr 2019.

Vancouver:

May JR. Studies of high temperature refractory fuels. [Internet] [Masters thesis]. University of New South Wales; 1960. [cited 2019 Apr 25]. Available from: http://handle.unsw.edu.au/1959.4/57170 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:42749/SOURCE02?view=true.

Council of Science Editors:

May JR. Studies of high temperature refractory fuels. [Masters Thesis]. University of New South Wales; 1960. Available from: http://handle.unsw.edu.au/1959.4/57170 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:42749/SOURCE02?view=true


University of New South Wales

22. Baillie, Malcolm. An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements.

Degree: Chemical Technology, Faculty of Applied Science, 1960, University of New South Wales

Subjects/Keywords: Nuclear fuels; Thesis Digitisation Program

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APA (6th Edition):

Baillie, M. (1960). An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements. (Masters Thesis). University of New South Wales. Retrieved from http://handle.unsw.edu.au/1959.4/57399 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:43363/SOURCE02?view=true

Chicago Manual of Style (16th Edition):

Baillie, Malcolm. “An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements.” 1960. Masters Thesis, University of New South Wales. Accessed April 25, 2019. http://handle.unsw.edu.au/1959.4/57399 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:43363/SOURCE02?view=true.

MLA Handbook (7th Edition):

Baillie, Malcolm. “An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements.” 1960. Web. 25 Apr 2019.

Vancouver:

Baillie M. An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements. [Internet] [Masters thesis]. University of New South Wales; 1960. [cited 2019 Apr 25]. Available from: http://handle.unsw.edu.au/1959.4/57399 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:43363/SOURCE02?view=true.

Council of Science Editors:

Baillie M. An investigation into the factors controlling the flooding point in liquid extraction as applied to the processing of a simulated solution of nuclear fuel elements. [Masters Thesis]. University of New South Wales; 1960. Available from: http://handle.unsw.edu.au/1959.4/57399 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:43363/SOURCE02?view=true


University of New South Wales

23. Alfredson, Peter George. A study of the variables in the coating of fuel particles in a fluidised bed.

Degree: Engineering, School of Nuclear Engineering, 1964, University of New South Wales

Subjects/Keywords: Nuclear fuels; Thesis Digitisation Program

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APA (6th Edition):

Alfredson, P. G. (1964). A study of the variables in the coating of fuel particles in a fluidised bed. (Masters Thesis). University of New South Wales. Retrieved from http://handle.unsw.edu.au/1959.4/56753 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41335/SOURCE02?view=true

Chicago Manual of Style (16th Edition):

Alfredson, Peter George. “A study of the variables in the coating of fuel particles in a fluidised bed.” 1964. Masters Thesis, University of New South Wales. Accessed April 25, 2019. http://handle.unsw.edu.au/1959.4/56753 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41335/SOURCE02?view=true.

MLA Handbook (7th Edition):

Alfredson, Peter George. “A study of the variables in the coating of fuel particles in a fluidised bed.” 1964. Web. 25 Apr 2019.

Vancouver:

Alfredson PG. A study of the variables in the coating of fuel particles in a fluidised bed. [Internet] [Masters thesis]. University of New South Wales; 1964. [cited 2019 Apr 25]. Available from: http://handle.unsw.edu.au/1959.4/56753 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41335/SOURCE02?view=true.

Council of Science Editors:

Alfredson PG. A study of the variables in the coating of fuel particles in a fluidised bed. [Masters Thesis]. University of New South Wales; 1964. Available from: http://handle.unsw.edu.au/1959.4/56753 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41335/SOURCE02?view=true


University of New South Wales

24. Magnusson, David John. Some theoretical studies of neutron distributions in various reactor systems.

Degree: Electrical Engineering:, 1960, University of New South Wales

Subjects/Keywords: Nuclear fuels; Thesis Digitisation Program

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APA (6th Edition):

Magnusson, D. J. (1960). Some theoretical studies of neutron distributions in various reactor systems. (Masters Thesis). University of New South Wales. Retrieved from http://handle.unsw.edu.au/1959.4/56759 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41373/SOURCE02?view=true

Chicago Manual of Style (16th Edition):

Magnusson, David John. “Some theoretical studies of neutron distributions in various reactor systems.” 1960. Masters Thesis, University of New South Wales. Accessed April 25, 2019. http://handle.unsw.edu.au/1959.4/56759 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41373/SOURCE02?view=true.

MLA Handbook (7th Edition):

Magnusson, David John. “Some theoretical studies of neutron distributions in various reactor systems.” 1960. Web. 25 Apr 2019.

Vancouver:

Magnusson DJ. Some theoretical studies of neutron distributions in various reactor systems. [Internet] [Masters thesis]. University of New South Wales; 1960. [cited 2019 Apr 25]. Available from: http://handle.unsw.edu.au/1959.4/56759 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41373/SOURCE02?view=true.

Council of Science Editors:

Magnusson DJ. Some theoretical studies of neutron distributions in various reactor systems. [Masters Thesis]. University of New South Wales; 1960. Available from: http://handle.unsw.edu.au/1959.4/56759 ; https://unsworks.unsw.edu.au/fapi/datastream/unsworks:41373/SOURCE02?view=true


University of Arizona

25. Schwarzblat, Morris, 1945-. AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS .

Degree: 1974, University of Arizona

Subjects/Keywords: Equations of state.; Nuclear fuels.

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APA (6th Edition):

Schwarzblat, Morris, 1. (1974). AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS . (Doctoral Dissertation). University of Arizona. Retrieved from http://hdl.handle.net/10150/288330

Chicago Manual of Style (16th Edition):

Schwarzblat, Morris, 1945-. “AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS .” 1974. Doctoral Dissertation, University of Arizona. Accessed April 25, 2019. http://hdl.handle.net/10150/288330.

MLA Handbook (7th Edition):

Schwarzblat, Morris, 1945-. “AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS .” 1974. Web. 25 Apr 2019.

Vancouver:

Schwarzblat, Morris 1. AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS . [Internet] [Doctoral dissertation]. University of Arizona; 1974. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/10150/288330.

Council of Science Editors:

Schwarzblat, Morris 1. AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS . [Doctoral Dissertation]. University of Arizona; 1974. Available from: http://hdl.handle.net/10150/288330


Kansas State University

26. Chen, Yuh-Fuu. A non-equilibrium LWR fuel cycle model.

Degree: 1973, Kansas State University

Subjects/Keywords: Nuclear fuels – Mathematical models

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APA (6th Edition):

Chen, Y. (1973). A non-equilibrium LWR fuel cycle model. (Thesis). Kansas State University. Retrieved from http://hdl.handle.net/2097/10687

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):

Chen, Yuh-Fuu. “A non-equilibrium LWR fuel cycle model.” 1973. Thesis, Kansas State University. Accessed April 25, 2019. http://hdl.handle.net/2097/10687.

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

MLA Handbook (7th Edition):

Chen, Yuh-Fuu. “A non-equilibrium LWR fuel cycle model.” 1973. Web. 25 Apr 2019.

Vancouver:

Chen Y. A non-equilibrium LWR fuel cycle model. [Internet] [Thesis]. Kansas State University; 1973. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/2097/10687.

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

Council of Science Editors:

Chen Y. A non-equilibrium LWR fuel cycle model. [Thesis]. Kansas State University; 1973. Available from: http://hdl.handle.net/2097/10687

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


Kansas State University

27. Johnson, William Joseph. Techniques for calculation of nuclear fuel costs.

Degree: 1976, Kansas State University

Subjects/Keywords: Nuclear fuels – Costs – Mathematics

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APA (6th Edition):

Johnson, W. J. (1976). Techniques for calculation of nuclear fuel costs. (Thesis). Kansas State University. Retrieved from http://hdl.handle.net/2097/11371

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):

Johnson, William Joseph. “Techniques for calculation of nuclear fuel costs.” 1976. Thesis, Kansas State University. Accessed April 25, 2019. http://hdl.handle.net/2097/11371.

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

MLA Handbook (7th Edition):

Johnson, William Joseph. “Techniques for calculation of nuclear fuel costs.” 1976. Web. 25 Apr 2019.

Vancouver:

Johnson WJ. Techniques for calculation of nuclear fuel costs. [Internet] [Thesis]. Kansas State University; 1976. [cited 2019 Apr 25]. Available from: http://hdl.handle.net/2097/11371.

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

Council of Science Editors:

Johnson WJ. Techniques for calculation of nuclear fuel costs. [Thesis]. Kansas State University; 1976. Available from: http://hdl.handle.net/2097/11371

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

28. Ivaldete da Silva Dupim. Hidretação do Zircaloy-4 para a obtenção de pó de Zr.

Degree: 2010, Universidade Federal do ABC

Nuclear fuels based on composite materials such as dispersion of uranium compounds in a Zirconium alloy matrix are possible alternatives for advanced nuclear generation technology.… (more)

Subjects/Keywords: Combustível Nuclear; Zircaloy-4; Zircaloy-4, Zr hydride, nuclear fuels; FISICA; Hidretação

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APA (6th Edition):

Dupim, I. d. S. (2010). Hidretação do Zircaloy-4 para a obtenção de pó de Zr. (Thesis). Universidade Federal do ABC. Retrieved from http://tede.ufabc.edu.br/tde_busca/arquivo.php?codArquivo=149

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):

Dupim, Ivaldete da Silva. “Hidretação do Zircaloy-4 para a obtenção de pó de Zr.” 2010. Thesis, Universidade Federal do ABC. Accessed April 25, 2019. http://tede.ufabc.edu.br/tde_busca/arquivo.php?codArquivo=149.

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

MLA Handbook (7th Edition):

Dupim, Ivaldete da Silva. “Hidretação do Zircaloy-4 para a obtenção de pó de Zr.” 2010. Web. 25 Apr 2019.

Vancouver:

Dupim IdS. Hidretação do Zircaloy-4 para a obtenção de pó de Zr. [Internet] [Thesis]. Universidade Federal do ABC; 2010. [cited 2019 Apr 25]. Available from: http://tede.ufabc.edu.br/tde_busca/arquivo.php?codArquivo=149.

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

Council of Science Editors:

Dupim IdS. Hidretação do Zircaloy-4 para a obtenção de pó de Zr. [Thesis]. Universidade Federal do ABC; 2010. Available from: http://tede.ufabc.edu.br/tde_busca/arquivo.php?codArquivo=149

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


Iowa State University

29. Madsen, Larry Charles. Nuclear fuel cycle cost analysis using parametric variation.

Degree: 1966, Iowa State University

Subjects/Keywords: Nuclear fuels – Costs; Nuclear Engineering; Engineering

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APA (6th Edition):

Madsen, L. C. (1966). Nuclear fuel cycle cost analysis using parametric variation. (Thesis). Iowa State University. Retrieved from https://lib.dr.iastate.edu/rtd/18487

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):

Madsen, Larry Charles. “Nuclear fuel cycle cost analysis using parametric variation.” 1966. Thesis, Iowa State University. Accessed April 25, 2019. https://lib.dr.iastate.edu/rtd/18487.

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

MLA Handbook (7th Edition):

Madsen, Larry Charles. “Nuclear fuel cycle cost analysis using parametric variation.” 1966. Web. 25 Apr 2019.

Vancouver:

Madsen LC. Nuclear fuel cycle cost analysis using parametric variation. [Internet] [Thesis]. Iowa State University; 1966. [cited 2019 Apr 25]. Available from: https://lib.dr.iastate.edu/rtd/18487.

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

Council of Science Editors:

Madsen LC. Nuclear fuel cycle cost analysis using parametric variation. [Thesis]. Iowa State University; 1966. Available from: https://lib.dr.iastate.edu/rtd/18487

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


University of Florida

30. Richard, Joshua. Analysis of the Neutron Source Term of a Spent Fuel Assembly.

Degree: 2010, University of Florida

Nuclear safeguards is primarily concerned with the detection of significant quantities of special nuclear material. Spent nuclear fuel offers a diversion pathway of significant quantities.… (more)

Subjects/Keywords: Assembly lines; Cell lines; Cooling; Data lines; Light water; Lines in space; Neutrons; Nuclides; Signals; Spent fuels; Neutron sources; Nuclear fuels

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APA (6th Edition):

Richard, J. (2010). Analysis of the Neutron Source Term of a Spent Fuel Assembly. (Thesis). University of Florida. Retrieved from http://ufdc.ufl.edu/AA00057162

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):

Richard, Joshua. “Analysis of the Neutron Source Term of a Spent Fuel Assembly.” 2010. Thesis, University of Florida. Accessed April 25, 2019. http://ufdc.ufl.edu/AA00057162.

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

MLA Handbook (7th Edition):

Richard, Joshua. “Analysis of the Neutron Source Term of a Spent Fuel Assembly.” 2010. Web. 25 Apr 2019.

Vancouver:

Richard J. Analysis of the Neutron Source Term of a Spent Fuel Assembly. [Internet] [Thesis]. University of Florida; 2010. [cited 2019 Apr 25]. Available from: http://ufdc.ufl.edu/AA00057162.

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

Council of Science Editors:

Richard J. Analysis of the Neutron Source Term of a Spent Fuel Assembly. [Thesis]. University of Florida; 2010. Available from: http://ufdc.ufl.edu/AA00057162

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

[1] [2] [3] [4] [5]

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