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You searched for subject:(NUCLEAR FUELS DEPLETION NUCLEAR ENGINEERING ). Showing records 1 – 30 of 227759 total matches.

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The Ohio State University

1. 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 October 21, 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. 21 Oct 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 Oct 21]. 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


Iowa State University

2. 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 October 21, 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. 21 Oct 2019.

Vancouver:

Madsen LC. Nuclear fuel cycle cost analysis using parametric variation. [Internet] [Thesis]. Iowa State University; 1966. [cited 2019 Oct 21]. 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


Oregon State University

3. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

4. 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 October 21, 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. 21 Oct 2019.

Vancouver:

Jenks RP. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 Oct 21]. 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

5. 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 October 21, 2019. http://hdl.handle.net/1957/41981.

MLA Handbook (7th Edition):

Montgomery, Scott D. “Thermal and mechanical behavior of sphere pac fuel.” 1982. Web. 21 Oct 2019.

Vancouver:

Montgomery SD. Thermal and mechanical behavior of sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2019 Oct 21]. 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

6. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

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 October 21, 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. 21 Oct 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 Oct 21]. 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. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

9. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

10. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

11. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

12. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

13. 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 October 21, 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. 21 Oct 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 Oct 21]. 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

14. 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 October 21, 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. 21 Oct 2019.

Vancouver:

Giefer DL. The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system. [Internet] [Thesis]. Kansas State University; 1974. [cited 2019 Oct 21]. 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


The Ohio State University

15. 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 October 21, 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. 21 Oct 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 Oct 21]. 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 Tennessee – Knoxville

16. Griswold, Justin Reed. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.

Degree: MS, Nuclear Engineering, 2014, University of Tennessee – Knoxville

  Actinium-225 is one of the more effective radioisotopes used in alpha radioimmunotherapy. Due to its ten-day half-life, it is more efficient to create its… (more)

Subjects/Keywords: Nuclear; Nuclear Engineering

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APA (6th Edition):

Griswold, J. R. (2014). Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/2820

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):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Thesis, University of Tennessee – Knoxville. Accessed October 21, 2019. https://trace.tennessee.edu/utk_gradthes/2820.

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

MLA Handbook (7th Edition):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Web. 21 Oct 2019.

Vancouver:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Internet] [Thesis]. University of Tennessee – Knoxville; 2014. [cited 2019 Oct 21]. Available from: https://trace.tennessee.edu/utk_gradthes/2820.

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

Council of Science Editors:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Thesis]. University of Tennessee – Knoxville; 2014. Available from: https://trace.tennessee.edu/utk_gradthes/2820

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


Texas A&M University

17. Shofolu, Babatunde Olayemi. Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope.

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

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Nuclear fuels.; Nuclear engineering - Computer programs.

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APA (6th Edition):

Shofolu, B. O. (2012). Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1990-THESIS-S559

Chicago Manual of Style (16th Edition):

Shofolu, Babatunde Olayemi. “Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1990-THESIS-S559.

MLA Handbook (7th Edition):

Shofolu, Babatunde Olayemi. “Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope.” 2012. Web. 21 Oct 2019.

Vancouver:

Shofolu BO. Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1990-THESIS-S559.

Council of Science Editors:

Shofolu BO. Nuclear fuel scoping: implementation of a four node per assembly algorithm as the neutronic module for microscope. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1990-THESIS-S559


Tartu University

18. 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 October 21, 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. 21 Oct 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 Oct 21]. 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


University of California – Berkeley

19. Cisneros, Anselmo Tomas. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).

Degree: Nuclear Engineering, 2013, University of California – Berkeley

 The Fluoride salt cooled High temperature Reactor (FHR) is a class of advanced nuclear reactors that combine the robust coated particle fuel form from high… (more)

Subjects/Keywords: Nuclear engineering; Advanced Reactor Design; Equilibrium Depletion; FHR; Liquid Salt; Pebble Bed Reactor

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APA (6th Edition):

Cisneros, A. T. (2013). Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/55h9183p

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):

Cisneros, Anselmo Tomas. “Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).” 2013. Thesis, University of California – Berkeley. Accessed October 21, 2019. http://www.escholarship.org/uc/item/55h9183p.

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

MLA Handbook (7th Edition):

Cisneros, Anselmo Tomas. “Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR).” 2013. Web. 21 Oct 2019.

Vancouver:

Cisneros AT. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). [Internet] [Thesis]. University of California – Berkeley; 2013. [cited 2019 Oct 21]. Available from: http://www.escholarship.org/uc/item/55h9183p.

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

Council of Science Editors:

Cisneros AT. Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR). [Thesis]. University of California – Berkeley; 2013. Available from: http://www.escholarship.org/uc/item/55h9183p

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


Texas A&M University

20. Hayes, Steven Lowe. Material property correlations for uranium mononitride.

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

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.; Uranium compounds.; Nuclear fuels - Computer simulation.; Nuclear reactors.

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APA (6th Edition):

Hayes, S. L. (2012). Material property correlations for uranium mononitride. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-H418

Chicago Manual of Style (16th Edition):

Hayes, Steven Lowe. “Material property correlations for uranium mononitride.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-H418.

MLA Handbook (7th Edition):

Hayes, Steven Lowe. “Material property correlations for uranium mononitride.” 2012. Web. 21 Oct 2019.

Vancouver:

Hayes SL. Material property correlations for uranium mononitride. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-H418.

Council of Science Editors:

Hayes SL. Material property correlations for uranium mononitride. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1989-THESIS-H418


Texas A&M University

21. 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 21, 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. 21 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 21]. 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


Texas A&M University

22. Taylor, Timothy. The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems.

Degree: 2010, Texas A&M University

 Interactions between societal, natural, and infrastructure systems can be beneficial or harmful to society. Society benefits from natural systems by being provided with the basic… (more)

Subjects/Keywords: public policy; nuclear power; stratospheric ozone depletion

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APA (6th Edition):

Taylor, T. (2010). The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-08-7006

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):

Taylor, Timothy. “The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems.” 2010. Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2009-08-7006.

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

MLA Handbook (7th Edition):

Taylor, Timothy. “The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems.” 2010. Web. 21 Oct 2019.

Vancouver:

Taylor T. The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-08-7006.

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

Council of Science Editors:

Taylor T. The Role of Science, Engineering, and Technology in the Public Policy Process for Infrastructure and Natural Systems. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-08-7006

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


Université Catholique de Louvain

23. Massinon, Lucien. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core.

Degree: 2018, Université Catholique de Louvain

The purpose of this master thesis consists in testing the ALEPH2 depletion code developed at the SCK-CEN, Mol, Belgium, on a new benchmark case and… (more)

Subjects/Keywords: ALEPH2; SCK-CEN; Depletion code; Nuclear physics

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APA (6th Edition):

Massinon, L. (2018). Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core. (Thesis). Université Catholique de Louvain. Retrieved from http://hdl.handle.net/2078.1/thesis:13305

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):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core.” 2018. Thesis, Université Catholique de Louvain. Accessed October 21, 2019. http://hdl.handle.net/2078.1/thesis:13305.

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

MLA Handbook (7th Edition):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core.” 2018. Web. 21 Oct 2019.

Vancouver:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core. [Internet] [Thesis]. Université Catholique de Louvain; 2018. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/2078.1/thesis:13305.

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

Council of Science Editors:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gosgen PWR core. [Thesis]. Université Catholique de Louvain; 2018. Available from: http://hdl.handle.net/2078.1/thesis:13305

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


Université Catholique de Louvain

24. Massinon, Lucien. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.

Degree: 2017, Université Catholique de Louvain

ALEPH is a Monte-Carlo burn-up code which is being developed in SCK-CEN (Studie Centrum voor de Kern energie - Centre d’Etude de l’énergie Nucléaire, Belgium)… (more)

Subjects/Keywords: ALEPH2; MCNP; nuclear science; depletion code

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APA (6th Edition):

Massinon, L. (2017). Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. (Thesis). Université Catholique de Louvain. Retrieved from http://hdl.handle.net/2078.1/thesis:13049

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):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.” 2017. Thesis, Université Catholique de Louvain. Accessed October 21, 2019. http://hdl.handle.net/2078.1/thesis:13049.

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

MLA Handbook (7th Edition):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.” 2017. Web. 21 Oct 2019.

Vancouver:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. [Internet] [Thesis]. Université Catholique de Louvain; 2017. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/2078.1/thesis:13049.

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

Council of Science Editors:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. [Thesis]. Université Catholique de Louvain; 2017. Available from: http://hdl.handle.net/2078.1/thesis:13049

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


Iowa State University

25. Montgomery, Leslie David. Thermal diffusivity of uranium dioxide.

Degree: 1963, Iowa State University

Subjects/Keywords: Nuclear fuels; Uranium dioxide; Thermal diffusivity; Nuclear Engineering; Engineering

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APA (6th Edition):

Montgomery, L. D. (1963). Thermal diffusivity of uranium dioxide. (Thesis). Iowa State University. Retrieved from https://lib.dr.iastate.edu/rtd/18575

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):

Montgomery, Leslie David. “Thermal diffusivity of uranium dioxide.” 1963. Thesis, Iowa State University. Accessed October 21, 2019. https://lib.dr.iastate.edu/rtd/18575.

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

MLA Handbook (7th Edition):

Montgomery, Leslie David. “Thermal diffusivity of uranium dioxide.” 1963. Web. 21 Oct 2019.

Vancouver:

Montgomery LD. Thermal diffusivity of uranium dioxide. [Internet] [Thesis]. Iowa State University; 1963. [cited 2019 Oct 21]. Available from: https://lib.dr.iastate.edu/rtd/18575.

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

Council of Science Editors:

Montgomery LD. Thermal diffusivity of uranium dioxide. [Thesis]. Iowa State University; 1963. Available from: https://lib.dr.iastate.edu/rtd/18575

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


Iowa State University

26. Crowther, Russell Lee. Slurry reactors.

Degree: 1955, Iowa State University

http://www.worldcat.org/oclc/37209888

Subjects/Keywords: Fluid fuel reactors; Nuclear fuels; Slurry; Nuclear Engineering; Engineering

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APA (6th Edition):

Crowther, R. L. (1955). Slurry reactors. (Thesis). Iowa State University. Retrieved from https://lib.dr.iastate.edu/rtd/18135

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):

Crowther, Russell Lee. “Slurry reactors.” 1955. Thesis, Iowa State University. Accessed October 21, 2019. https://lib.dr.iastate.edu/rtd/18135.

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

MLA Handbook (7th Edition):

Crowther, Russell Lee. “Slurry reactors.” 1955. Web. 21 Oct 2019.

Vancouver:

Crowther RL. Slurry reactors. [Internet] [Thesis]. Iowa State University; 1955. [cited 2019 Oct 21]. Available from: https://lib.dr.iastate.edu/rtd/18135.

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

Council of Science Editors:

Crowther RL. Slurry reactors. [Thesis]. Iowa State University; 1955. Available from: https://lib.dr.iastate.edu/rtd/18135

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


Texas A&M University

27. Ragusa, Jean Concetto. Accelerator driven production of tritium: target and blanket design.

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

 Tritium is an essential component of thermonuclear weapons in the US arsenal. Unfortunately, tritium is a radioactive form of hydrogen, and one-half of the inventory… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ragusa, J. C. (2012). Accelerator driven production of tritium: target and blanket design. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34

Chicago Manual of Style (16th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

MLA Handbook (7th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Web. 21 Oct 2019.

Vancouver:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

Council of Science Editors:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34


Texas A&M University

28. Ramone, Gilles Lionel. A Transport Synthetic Acceleration method for transport iterations.

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

 We present a family of Transport Synthetic Acceleration (TSA) methods to iteratively solve within-group scattering problems. A single iteration in these schemes consists of a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ramone, G. L. (2012). A Transport Synthetic Acceleration method for transport iterations. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365

Chicago Manual of Style (16th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

MLA Handbook (7th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Web. 21 Oct 2019.

Vancouver:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

Council of Science Editors:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365


Texas A&M University

29. Reyes, Joseph Patrick. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.

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

 The modeling of the complex thermal hydraulics of reactor systems involves the use of experimental test systems as well as numerical codes. A simulation of… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Reyes, J. P. (2012). Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49

Chicago Manual of Style (16th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

MLA Handbook (7th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Web. 21 Oct 2019.

Vancouver:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

Council of Science Editors:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49


Texas A&M University

30. Troshko, Andrey Arthurovich. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.

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

 Assessment of the ability of thermal hydraulic codes to correctly predict complex phenomena during reactor transients can be performed only by means of comparison against… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Troshko, A. A. (2012). Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76

Chicago Manual of Style (16th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Masters Thesis, Texas A&M University. Accessed October 21, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

MLA Handbook (7th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Web. 21 Oct 2019.

Vancouver:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Oct 21]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

Council of Science Editors:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76

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