Advanced search options

Advanced Search Options 🞨

Browse by author name (“Author name starts with…”).

Find ETDs with:

in
/  
in
/  
in
/  
in

Written in Published in Earliest date Latest date

Sorted by

Results per page:

Sorted by: relevance · author · university · dateNew search

You searched for subject:(Nuclear fuels). Showing records 1 – 30 of 161 total matches.

[1] [2] [3] [4] [5] [6]

Search Limiters

Last 2 Years | English Only

Degrees

Levels

Languages

Country

▼ Search Limiters


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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Jenks RP. Direct shear testing of UO₂ sphere-pac nuclear reactor fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. http://hdl.handle.net/1957/41981.

MLA Handbook (7th Edition):

Montgomery, Scott D. “Thermal and mechanical behavior of sphere pac fuel.” 1982. Web. 18 Apr 2021.

Vancouver:

Montgomery SD. Thermal and mechanical behavior of sphere pac fuel. [Internet] [Masters thesis]. Oregon State University; 1982. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Nielsen LH. An assessment of describing function methods applied to reactor fuel performance analysis. [Internet] [Masters thesis]. Oregon State University; 1980. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Bailey WJ. Investigation of plutonium-bearing fuel elements for the plutonium recycle test reactor (PRTR). [Internet] [Masters thesis]. Oregon State University; 1960. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Stout RB. Optimization of in-core nuclear fuel management in a pressurized water reactor. [Internet] [Doctoral dissertation]. Oregon State University; 1972. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Giefer DL. The irradiation effects on a model TBP-decahydranaphthalene solvent extraction system. [Internet] [Thesis]. Kansas State University; 1974. [cited 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Azarfar MA. A methodology for safeguards evaluation and its application to mixed oxide fuel fabrication. [Internet] [Doctoral dissertation]. Oregon State University; 1982. [cited 2021 Apr 18]. 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


University of Arizona

15. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. http://hdl.handle.net/10150/277150.

MLA Handbook (7th Edition):

Smith, Adrienne Bobbette, 1960-. “Nuclear excursions in aqueous solutions of fissile materials .” 1989. Web. 18 Apr 2021.

Vancouver:

Smith, Adrienne Bobbette 1. Nuclear excursions in aqueous solutions of fissile materials . [Internet] [Masters thesis]. University of Arizona; 1989. [cited 2021 Apr 18]. 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


University of Texas – Austin

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

Degree: PhD, 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Matavosian, Robert. “Complex problems arising in the collision probability theory for neutron transport.” 2007. Doctoral Dissertation, University of Texas – Austin. Accessed April 18, 2021. http://hdl.handle.net/2152/3789.

MLA Handbook (7th Edition):

Matavosian, Robert. “Complex problems arising in the collision probability theory for neutron transport.” 2007. Web. 18 Apr 2021.

Vancouver:

Matavosian R. Complex problems arising in the collision probability theory for neutron transport. [Internet] [Doctoral dissertation]. University of Texas – Austin; 2007. [cited 2021 Apr 18]. Available from: http://hdl.handle.net/2152/3789.

Council of Science Editors:

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


The Ohio State University

17. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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 South Carolina

18. Yingling, Jacob A. Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding.

Degree: Degree ofMSin Nuclear Engineering, Nuclear Engineering, 2019, University of South Carolina

  Accident Tolerant Fuels (ATF) require a combination of fuel and cladding which have comparable longevity characteristics to UO2 while improving resistance to radiological release… (more)

Subjects/Keywords: Nuclear Engineering; Bison; U3SI2; U3SI2 Fuels; Composite-Monolithic Duplex; SIC; Accident Tolerant Fuels

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Yingling, J. A. (2019). Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding. (Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/5513

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):

Yingling, Jacob A. “Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding.” 2019. Thesis, University of South Carolina. Accessed April 18, 2021. https://scholarcommons.sc.edu/etd/5513.

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

MLA Handbook (7th Edition):

Yingling, Jacob A. “Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding.” 2019. Web. 18 Apr 2021.

Vancouver:

Yingling JA. Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding. [Internet] [Thesis]. University of South Carolina; 2019. [cited 2021 Apr 18]. Available from: https://scholarcommons.sc.edu/etd/5513.

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

Council of Science Editors:

Yingling JA. Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding. [Thesis]. University of South Carolina; 2019. Available from: https://scholarcommons.sc.edu/etd/5513

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


Colorado School of Mines

19. Worrall, Michael Jason. Feasibility study of a small, thorium-based fission power system for space and terrestrial applications.

Degree: PhD, Physics, 2013, Colorado School of Mines

 One of the current challenges facing space exploration is the creation of a power source capable of providing useful energy for the entire duration of… (more)

Subjects/Keywords: reactor; modular; thorium; space; Thorium; Nuclear fission; Nuclear reactors; Nuclear energy; Nuclear fuels; Outer space  – Exploration

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Worrall, M. J. (2013). Feasibility study of a small, thorium-based fission power system for space and terrestrial applications. (Doctoral Dissertation). Colorado School of Mines. Retrieved from http://hdl.handle.net/11124/2

Chicago Manual of Style (16th Edition):

Worrall, Michael Jason. “Feasibility study of a small, thorium-based fission power system for space and terrestrial applications.” 2013. Doctoral Dissertation, Colorado School of Mines. Accessed April 18, 2021. http://hdl.handle.net/11124/2.

MLA Handbook (7th Edition):

Worrall, Michael Jason. “Feasibility study of a small, thorium-based fission power system for space and terrestrial applications.” 2013. Web. 18 Apr 2021.

Vancouver:

Worrall MJ. Feasibility study of a small, thorium-based fission power system for space and terrestrial applications. [Internet] [Doctoral dissertation]. Colorado School of Mines; 2013. [cited 2021 Apr 18]. Available from: http://hdl.handle.net/11124/2.

Council of Science Editors:

Worrall MJ. Feasibility study of a small, thorium-based fission power system for space and terrestrial applications. [Doctoral Dissertation]. Colorado School of Mines; 2013. Available from: http://hdl.handle.net/11124/2

20. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Dupim IdS. Hidretação do Zircaloy-4 para a obtenção de pó de Zr. [Internet] [Thesis]. Universidade Federal do ABC; 2010. [cited 2021 Apr 18]. 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

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

Degree: 1966, Iowa State University

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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Madsen LC. Nuclear fuel cycle cost analysis using parametric variation. [Internet] [Thesis]. Iowa State University; 1966. [cited 2021 Apr 18]. 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


Colorado School of Mines

22. Davis, Brian Campbell. Fracture strength of the SiC layer in TRISO coated fuel particles.

Degree: MS(M.S.), Mechanical Engineering, 2013, Colorado School of Mines

 The SiC layer in the TRISO coating of next generation nuclear fuel particles is a structural element which ensures the containment of fissile products, thus… (more)

Subjects/Keywords: TRISO; NGNP; Nuclear fuels  – Transportation; Particles (Nuclear physics); Coating processes; Silicon carbide

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Davis, B. C. (2013). Fracture strength of the SiC layer in TRISO coated fuel particles. (Masters Thesis). Colorado School of Mines. Retrieved from http://hdl.handle.net/11124/78777

Chicago Manual of Style (16th Edition):

Davis, Brian Campbell. “Fracture strength of the SiC layer in TRISO coated fuel particles.” 2013. Masters Thesis, Colorado School of Mines. Accessed April 18, 2021. http://hdl.handle.net/11124/78777.

MLA Handbook (7th Edition):

Davis, Brian Campbell. “Fracture strength of the SiC layer in TRISO coated fuel particles.” 2013. Web. 18 Apr 2021.

Vancouver:

Davis BC. Fracture strength of the SiC layer in TRISO coated fuel particles. [Internet] [Masters thesis]. Colorado School of Mines; 2013. [cited 2021 Apr 18]. Available from: http://hdl.handle.net/11124/78777.

Council of Science Editors:

Davis BC. Fracture strength of the SiC layer in TRISO coated fuel particles. [Masters Thesis]. Colorado School of Mines; 2013. Available from: http://hdl.handle.net/11124/78777

23. LEVY, DENISE S. Contribuição para informatização dos programas de proteção radiológica para instalações radiativas.

Degree: 2012, Brazil

Made available in DSpace on 2014-10-09T12:35:14Z (GMT). No. of bitstreams: 0

Made available in DSpace on 2014-10-09T14:09:36Z (GMT). No. of bitstreams: 0

Para elaborar um… (more)

Subjects/Keywords: radiation protection; nuclear facilities; nuclear fuels; fuel cycle; computerized control systems; computer codes; program management

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

LEVY, D. S. (2012). Contribuição para informatização dos programas de proteção radiológica para instalações radiativas. (Masters Thesis). Brazil. Retrieved from http://repositorio.ipen.br:8080/xmlui/handle/123456789/10144

Chicago Manual of Style (16th Edition):

LEVY, DENISE S. “Contribuição para informatização dos programas de proteção radiológica para instalações radiativas.” 2012. Masters Thesis, Brazil. Accessed April 18, 2021. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10144.

MLA Handbook (7th Edition):

LEVY, DENISE S. “Contribuição para informatização dos programas de proteção radiológica para instalações radiativas.” 2012. Web. 18 Apr 2021.

Vancouver:

LEVY DS. Contribuição para informatização dos programas de proteção radiológica para instalações radiativas. [Internet] [Masters thesis]. Brazil; 2012. [cited 2021 Apr 18]. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10144.

Council of Science Editors:

LEVY DS. Contribuição para informatização dos programas de proteção radiológica para instalações radiativas. [Masters Thesis]. Brazil; 2012. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10144


Universidade Estadual de Campinas

24. Bianchessi, Luis Francisco, 1990-. Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel.

Degree: Instituto de Química; Programa de Pós-Graduação em Química, 2019, Universidade Estadual de Campinas

Orientador: Matthieu Tubino

Dissertação (mestrado) - Universidade Estadual de Campinas, Instituto de Química

Made available in DSpace on 2020-01-30T18:29:58Z (GMT). No. of bitstreams: 1 Bianchessi_LuisFrancisco_M.pdf:… (more)

Subjects/Keywords: Biodiesel; Síntese; Blendas; Ressonância magnética nuclear; Biodiesel fuels; Synthesis; Blends; Nuclear magnetic resonance

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Bianchessi, Luis Francisco, 1. (2019). Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel. (Masters Thesis). Universidade Estadual de Campinas. Retrieved from http://repositorio.unicamp.br/jspui/handle/REPOSIP/335866

Chicago Manual of Style (16th Edition):

Bianchessi, Luis Francisco, 1990-. “Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel.” 2019. Masters Thesis, Universidade Estadual de Campinas. Accessed April 18, 2021. http://repositorio.unicamp.br/jspui/handle/REPOSIP/335866.

MLA Handbook (7th Edition):

Bianchessi, Luis Francisco, 1990-. “Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel.” 2019. Web. 18 Apr 2021.

Vancouver:

Bianchessi, Luis Francisco 1. Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel. [Internet] [Masters thesis]. Universidade Estadual de Campinas; 2019. [cited 2021 Apr 18]. Available from: http://repositorio.unicamp.br/jspui/handle/REPOSIP/335866.

Council of Science Editors:

Bianchessi, Luis Francisco 1. Estudos relativos à síntese de biodiesel e avaliação de blendas diesel-biodiesel. [Masters Thesis]. Universidade Estadual de Campinas; 2019. Available from: http://repositorio.unicamp.br/jspui/handle/REPOSIP/335866


University of Bath

25. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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://researchportal.bath.ac.uk/en/studentthesis/evaluation-of-a-technique-for-the-remote-measurement-of-surface-temperature-distributions-in-laser-heated-samples(a9095f76-bfcb-486d-a5be-9eba36ed654c).html ; 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 18, 2021. https://researchportal.bath.ac.uk/en/studentthesis/evaluation-of-a-technique-for-the-remote-measurement-of-surface-temperature-distributions-in-laser-heated-samples(a9095f76-bfcb-486d-a5be-9eba36ed654c).html ; 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. 18 Apr 2021.

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 2021 Apr 18]. Available from: https://researchportal.bath.ac.uk/en/studentthesis/evaluation-of-a-technique-for-the-remote-measurement-of-surface-temperature-distributions-in-laser-heated-samples(a9095f76-bfcb-486d-a5be-9eba36ed654c).html ; 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://researchportal.bath.ac.uk/en/studentthesis/evaluation-of-a-technique-for-the-remote-measurement-of-surface-temperature-distributions-in-laser-heated-samples(a9095f76-bfcb-486d-a5be-9eba36ed654c).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.320437


University of Arizona

26. 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.

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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 Arizona

27. 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.

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Schwarzblat, Morris 1. AN EQUATION OF STATE FOR MIXED-OXIDE FAST REACTOR FUELS . [Internet] [Doctoral dissertation]. University of Arizona; 1974. [cited 2021 Apr 18]. 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

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

Degree: 1976, Kansas State University

Subjects/Keywords: Nuclear fuels – Costs – Mathematics

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Johnson WJ. Techniques for calculation of nuclear fuel costs. [Internet] [Thesis]. Kansas State University; 1976. [cited 2021 Apr 18]. 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


Kansas State University

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

Degree: 1973, Kansas State University

Subjects/Keywords: Nuclear fuels – Mathematical models

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

Vancouver:

Chen Y. A non-equilibrium LWR fuel cycle model. [Internet] [Thesis]. Kansas State University; 1973. [cited 2021 Apr 18]. 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


University of New South Wales

30. 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

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

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 18, 2021. 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. 18 Apr 2021.

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 2021 Apr 18]. 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

[1] [2] [3] [4] [5] [6]

.