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You searched for +publisher:"Oregon State University" +contributor:("Peddicord, K. L."). Showing records 1 – 14 of 14 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 May 19, 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. 19 May 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 May 19]. 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. Vincent, Andrew M. Fuel-cladding mechanical interaction in simulated sphere pac fuel.

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

 A study has been made to investigate the fuel-cladding mechanical interaction (FCMI) in sphere pac fuels. An FCMI simulation has been constructed using the JVG… (more)

Subjects/Keywords: Nuclear fuel claddings

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APA (6th Edition):

Vincent, A. M. (1981). Fuel-cladding mechanical interaction in simulated sphere pac fuel. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/41696

Chicago Manual of Style (16th Edition):

Vincent, Andrew M. “Fuel-cladding mechanical interaction in simulated sphere pac fuel.” 1981. Masters Thesis, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/41696.

MLA Handbook (7th Edition):

Vincent, Andrew M. “Fuel-cladding mechanical interaction in simulated sphere pac fuel.” 1981. Web. 19 May 2019.

Vancouver:

Vincent AM. Fuel-cladding mechanical interaction in simulated sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/41696.

Council of Science Editors:

Vincent AM. Fuel-cladding mechanical interaction in simulated sphere pac fuel. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/41696


Oregon State University

3. 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 May 19, 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. 19 May 2019.

Vancouver:

Willison JS. Thermal conductivity modeling of unrestructured sphere pac nuclear fuels. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 May 19]. 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


Oregon State University

4. 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 May 19, 2019. http://hdl.handle.net/1957/41981.

MLA Handbook (7th Edition):

Montgomery, Scott D. “Thermal and mechanical behavior of sphere pac fuel.” 1982. Web. 19 May 2019.

Vancouver:

Montgomery SD. Thermal and mechanical behavior of sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 May 19]. 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

5. 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 May 19, 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. 19 May 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 May 19]. 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

6. Coomes, Edmund Page. Thermal hydraulic analysis of a pressurized water reactor during transient conditions.

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

 In this study a method has been demonstrated by which the departure from nucleate boiling ratio (DNBR) can be readily determined for nuclear transients through… (more)

Subjects/Keywords: Water boiler reactors

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APA (6th Edition):

Coomes, E. P. (1980). Thermal hydraulic analysis of a pressurized water reactor during transient conditions. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42423

Chicago Manual of Style (16th Edition):

Coomes, Edmund Page. “Thermal hydraulic analysis of a pressurized water reactor during transient conditions.” 1980. Masters Thesis, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/42423.

MLA Handbook (7th Edition):

Coomes, Edmund Page. “Thermal hydraulic analysis of a pressurized water reactor during transient conditions.” 1980. Web. 19 May 2019.

Vancouver:

Coomes EP. Thermal hydraulic analysis of a pressurized water reactor during transient conditions. [Internet] [Masters thesis]. Oregon State University; 1980. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/42423.

Council of Science Editors:

Coomes EP. Thermal hydraulic analysis of a pressurized water reactor during transient conditions. [Masters Thesis]. Oregon State University; 1980. Available from: http://hdl.handle.net/1957/42423


Oregon State University

7. 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 May 19, 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. 19 May 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 May 19]. 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

8. Oylear, Joan Marie. Thermal hydraulic analysis of a pressurized water reactor.

Degree: MS, Nuclear Engineering, 1979, Oregon State University

Subjects/Keywords: Pressurized water reactors

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APA (6th Edition):

Oylear, J. M. (1979). Thermal hydraulic analysis of a pressurized water reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42507

Chicago Manual of Style (16th Edition):

Oylear, Joan Marie. “Thermal hydraulic analysis of a pressurized water reactor.” 1979. Masters Thesis, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/42507.

MLA Handbook (7th Edition):

Oylear, Joan Marie. “Thermal hydraulic analysis of a pressurized water reactor.” 1979. Web. 19 May 2019.

Vancouver:

Oylear JM. Thermal hydraulic analysis of a pressurized water reactor. [Internet] [Masters thesis]. Oregon State University; 1979. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/42507.

Council of Science Editors:

Oylear JM. Thermal hydraulic analysis of a pressurized water reactor. [Masters Thesis]. Oregon State University; 1979. Available from: http://hdl.handle.net/1957/42507


Oregon State University

9. Ades, Maurice. Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel.

Degree: PhD, Nuclear Engineering, 1979, Oregon State University

 Several fuels are being investigated for fast breeder reactor applications. One promising concept is sphere-pac mixed carbide fuel. As a part of the development of… (more)

Subjects/Keywords: Nuclear fuels  – Effect of radiation on

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APA (6th Edition):

Ades, M. (1979). Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/43157

Chicago Manual of Style (16th Edition):

Ades, Maurice. “Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel.” 1979. Doctoral Dissertation, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/43157.

MLA Handbook (7th Edition):

Ades, Maurice. “Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel.” 1979. Web. 19 May 2019.

Vancouver:

Ades M. Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel. [Internet] [Doctoral dissertation]. Oregon State University; 1979. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/43157.

Council of Science Editors:

Ades M. Modeling of the thermal behavior of irradiated sphere-pac mixed carbide fuel. [Doctoral Dissertation]. Oregon State University; 1979. Available from: http://hdl.handle.net/1957/43157


Oregon State University

10. McNair, Gary W. An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets.

Degree: MS, IN Nuclear Engineering, 1977, Oregon State University

 In fuel pin fabrication, there is no assurance that a fuel pellet will be loaded concentrically. Therefore, azimuthal variations exist in the temperature field giving… (more)

Subjects/Keywords: Heat  – Transmission

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APA (6th Edition):

McNair, G. W. (1977). An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/43601

Chicago Manual of Style (16th Edition):

McNair, Gary W. “An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets.” 1977. Masters Thesis, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/43601.

MLA Handbook (7th Edition):

McNair, Gary W. “An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets.” 1977. Web. 19 May 2019.

Vancouver:

McNair GW. An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets. [Internet] [Masters thesis]. Oregon State University; 1977. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/43601.

Council of Science Editors:

McNair GW. An evaluation of finite difference methods for calculating heat transfer in fuel pins with eccentrically placed pellets. [Masters Thesis]. Oregon State University; 1977. Available from: http://hdl.handle.net/1957/43601


Oregon State University

11. Robinson, Cheryl A. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.

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

 Through a joint effort by the Swiss Federal Institute for Reactor Research and Oregon State University, the fuels modeling code SPECKLE is being developed to… (more)

Subjects/Keywords: Neutron flux

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APA (6th Edition):

Robinson, C. A. (1981). Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42178

Chicago Manual of Style (16th Edition):

Robinson, Cheryl A. “Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.” 1981. Masters Thesis, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/42178.

MLA Handbook (7th Edition):

Robinson, Cheryl A. “Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.” 1981. Web. 19 May 2019.

Vancouver:

Robinson CA. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/42178.

Council of Science Editors:

Robinson CA. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/42178


Oregon State University

12. Nassersharif, Bahram. Describing function theory as applied to thermal and neutronic problems.

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

 Describing functions have traditionally been used to obtain the solutions of systems of ordinary differential equations. In this work the describing function concept has been… (more)

Subjects/Keywords: Nuclear engineering  – Mathematics

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APA (6th Edition):

Nassersharif, B. (1982). Describing function theory as applied to thermal and neutronic problems. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/41102

Chicago Manual of Style (16th Edition):

Nassersharif, Bahram. “Describing function theory as applied to thermal and neutronic problems.” 1982. Doctoral Dissertation, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/41102.

MLA Handbook (7th Edition):

Nassersharif, Bahram. “Describing function theory as applied to thermal and neutronic problems.” 1982. Web. 19 May 2019.

Vancouver:

Nassersharif B. Describing function theory as applied to thermal and neutronic problems. [Internet] [Doctoral dissertation]. Oregon State University; 1982. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/41102.

Council of Science Editors:

Nassersharif B. Describing function theory as applied to thermal and neutronic problems. [Doctoral Dissertation]. Oregon State University; 1982. Available from: http://hdl.handle.net/1957/41102


Oregon State University

13. 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 May 19, 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. 19 May 2019.

Vancouver:

Jenks RP. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 May 19]. 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

14. Ting, Yine-ping. Heat conduction in eccentric annuli.

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

 Muitiregion annular geometry is a basic feature of energy removal systems ranging from advanced heat exchangers to fission reactor fuel rods. For the symmetric cases,… (more)

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APA (6th Edition):

Ting, Y. (1981). Heat conduction in eccentric annuli. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/42157

Chicago Manual of Style (16th Edition):

Ting, Yine-ping. “Heat conduction in eccentric annuli.” 1981. Doctoral Dissertation, Oregon State University. Accessed May 19, 2019. http://hdl.handle.net/1957/42157.

MLA Handbook (7th Edition):

Ting, Yine-ping. “Heat conduction in eccentric annuli.” 1981. Web. 19 May 2019.

Vancouver:

Ting Y. Heat conduction in eccentric annuli. [Internet] [Doctoral dissertation]. Oregon State University; 1981. [cited 2019 May 19]. Available from: http://hdl.handle.net/1957/42157.

Council of Science Editors:

Ting Y. Heat conduction in eccentric annuli. [Doctoral Dissertation]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/42157

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