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You searched for subject:(Nuclear reactors). Showing records 1 – 30 of 494 total matches.

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Addis Ababa University

1. Belachew, Dessalegn. NUCLEAR REACTORS .

Degree: 2012, Addis Ababa University

Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain… (more)

Subjects/Keywords: NUCLEAR; REACTORS

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APA (6th Edition):

Belachew, D. (2012). NUCLEAR REACTORS . (Thesis). Addis Ababa University. Retrieved from http://etd.aau.edu.et/dspace/handle/123456789/1274

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):

Belachew, Dessalegn. “NUCLEAR REACTORS .” 2012. Thesis, Addis Ababa University. Accessed February 17, 2019. http://etd.aau.edu.et/dspace/handle/123456789/1274.

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

MLA Handbook (7th Edition):

Belachew, Dessalegn. “NUCLEAR REACTORS .” 2012. Web. 17 Feb 2019.

Vancouver:

Belachew D. NUCLEAR REACTORS . [Internet] [Thesis]. Addis Ababa University; 2012. [cited 2019 Feb 17]. Available from: http://etd.aau.edu.et/dspace/handle/123456789/1274.

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

Council of Science Editors:

Belachew D. NUCLEAR REACTORS . [Thesis]. Addis Ababa University; 2012. Available from: http://etd.aau.edu.et/dspace/handle/123456789/1274

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


Oregon State University

2. Marcum, Wade R. Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D.

Degree: MS, Nuclear Engineering, 2008, Oregon State University

 Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals… (more)

Subjects/Keywords: Nuclear; TRIGA reactors

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APA (6th Edition):

Marcum, W. R. (2008). Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/8272

Chicago Manual of Style (16th Edition):

Marcum, Wade R. “Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D.” 2008. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/8272.

MLA Handbook (7th Edition):

Marcum, Wade R. “Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D.” 2008. Web. 17 Feb 2019.

Vancouver:

Marcum WR. Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/8272.

Council of Science Editors:

Marcum WR. Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/8272


Oregon State University

3. Jackson, R. Brian. A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code.

Degree: MS, Nuclear Engineering, 2008, Oregon State University

 Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was… (more)

Subjects/Keywords: Nuclear; Nuclear reactors  – Fluid dynamics

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APA (6th Edition):

Jackson, R. B. (2008). A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/8338

Chicago Manual of Style (16th Edition):

Jackson, R Brian. “A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code.” 2008. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/8338.

MLA Handbook (7th Edition):

Jackson, R Brian. “A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code.” 2008. Web. 17 Feb 2019.

Vancouver:

Jackson RB. A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/8338.

Council of Science Editors:

Jackson RB. A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/8338


Oregon State University

4. Park, Jin Yong. Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles.

Degree: PhD, Chemical Engineering, 1976, Oregon State University

 This thesis consists of two parts. Part I (Chapters 1, 2, 3) of this thesis concerns finding the best way of running a reactor whose… (more)

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Park, J. Y. (1976). Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/14340

Chicago Manual of Style (16th Edition):

Park, Jin Yong. “Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles.” 1976. Doctoral Dissertation, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/14340.

MLA Handbook (7th Edition):

Park, Jin Yong. “Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles.” 1976. Web. 17 Feb 2019.

Vancouver:

Park JY. Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles. [Internet] [Doctoral dissertation]. Oregon State University; 1976. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/14340.

Council of Science Editors:

Park JY. Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles. [Doctoral Dissertation]. Oregon State University; 1976. Available from: http://hdl.handle.net/1957/14340


Oregon State University

5. Meck, Robert Allen. Argon-41 production by the OSU TRIGA III reactor.

Degree: MS, General Science, 1967, Oregon State University

 A sensitive ion chamber-electrometer system was used to determine the Oregon State University TRIGA III reactor's ⁴¹Ar production rate as a function of steady state… (more)

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Meck, R. A. (1967). Argon-41 production by the OSU TRIGA III reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/47045

Chicago Manual of Style (16th Edition):

Meck, Robert Allen. “Argon-41 production by the OSU TRIGA III reactor.” 1967. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/47045.

MLA Handbook (7th Edition):

Meck, Robert Allen. “Argon-41 production by the OSU TRIGA III reactor.” 1967. Web. 17 Feb 2019.

Vancouver:

Meck RA. Argon-41 production by the OSU TRIGA III reactor. [Internet] [Masters thesis]. Oregon State University; 1967. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/47045.

Council of Science Editors:

Meck RA. Argon-41 production by the OSU TRIGA III reactor. [Masters Thesis]. Oregon State University; 1967. Available from: http://hdl.handle.net/1957/47045


University of Arizona

6. Curtis, Robert Thornton, 1923-. A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity .

Degree: 1961, University of Arizona

Subjects/Keywords: Nuclear reactors.

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APA (6th Edition):

Curtis, Robert Thornton, 1. (1961). A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/348334

Chicago Manual of Style (16th Edition):

Curtis, Robert Thornton, 1923-. “A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity .” 1961. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/348334.

MLA Handbook (7th Edition):

Curtis, Robert Thornton, 1923-. “A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity .” 1961. Web. 17 Feb 2019.

Vancouver:

Curtis, Robert Thornton 1. A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity . [Internet] [Masters thesis]. University of Arizona; 1961. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/348334.

Council of Science Editors:

Curtis, Robert Thornton 1. A method of determining the reactor transfer function from an analysis of the reactor's response to a step change in reactivity . [Masters Thesis]. University of Arizona; 1961. Available from: http://hdl.handle.net/10150/348334


University of Arizona

7. Backus, Charles E., 1937-. The design, construction, and testing of the University of Arizona subcritical reactor .

Degree: 1961, University of Arizona

Subjects/Keywords: Nuclear reactors.

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APA (6th Edition):

Backus, Charles E., 1. (1961). The design, construction, and testing of the University of Arizona subcritical reactor . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/551543

Chicago Manual of Style (16th Edition):

Backus, Charles E., 1937-. “The design, construction, and testing of the University of Arizona subcritical reactor .” 1961. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/551543.

MLA Handbook (7th Edition):

Backus, Charles E., 1937-. “The design, construction, and testing of the University of Arizona subcritical reactor .” 1961. Web. 17 Feb 2019.

Vancouver:

Backus, Charles E. 1. The design, construction, and testing of the University of Arizona subcritical reactor . [Internet] [Masters thesis]. University of Arizona; 1961. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/551543.

Council of Science Editors:

Backus, Charles E. 1. The design, construction, and testing of the University of Arizona subcritical reactor . [Masters Thesis]. University of Arizona; 1961. Available from: http://hdl.handle.net/10150/551543


University of Arizona

8. Jinamornphongs, Prachaks, 1938-. Power pulse measurement and analysis for a TRIGA reactor .

Degree: 1973, University of Arizona

Subjects/Keywords: Nuclear reactors.

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APA (6th Edition):

Jinamornphongs, Prachaks, 1. (1973). Power pulse measurement and analysis for a TRIGA reactor . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/554575

Chicago Manual of Style (16th Edition):

Jinamornphongs, Prachaks, 1938-. “Power pulse measurement and analysis for a TRIGA reactor .” 1973. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/554575.

MLA Handbook (7th Edition):

Jinamornphongs, Prachaks, 1938-. “Power pulse measurement and analysis for a TRIGA reactor .” 1973. Web. 17 Feb 2019.

Vancouver:

Jinamornphongs, Prachaks 1. Power pulse measurement and analysis for a TRIGA reactor . [Internet] [Masters thesis]. University of Arizona; 1973. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/554575.

Council of Science Editors:

Jinamornphongs, Prachaks 1. Power pulse measurement and analysis for a TRIGA reactor . [Masters Thesis]. University of Arizona; 1973. Available from: http://hdl.handle.net/10150/554575


Montana State University

9. Russell, Gary James. Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly.

Degree: College of Letters & Science, 1962, Montana State University

Subjects/Keywords: Nuclear reactors.

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APA (6th Edition):

Russell, G. J. (1962). Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly. (Thesis). Montana State University. Retrieved from https://scholarworks.montana.edu/xmlui/handle/1/6013

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):

Russell, Gary James. “Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly.” 1962. Thesis, Montana State University. Accessed February 17, 2019. https://scholarworks.montana.edu/xmlui/handle/1/6013.

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

MLA Handbook (7th Edition):

Russell, Gary James. “Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly.” 1962. Web. 17 Feb 2019.

Vancouver:

Russell GJ. Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly. [Internet] [Thesis]. Montana State University; 1962. [cited 2019 Feb 17]. Available from: https://scholarworks.montana.edu/xmlui/handle/1/6013.

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

Council of Science Editors:

Russell GJ. Determination of the temperature coefficient of reactivity of the Montana State College subcritical assembly. [Thesis]. Montana State University; 1962. Available from: https://scholarworks.montana.edu/xmlui/handle/1/6013

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


Montana State University

10. Chowdhury, Tushar Kumar. The determination of reactor parameters of the Montana State College sub-critical assembly.

Degree: College of Letters & Science, 1961, Montana State University

Subjects/Keywords: Nuclear reactors.

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APA (6th Edition):

Chowdhury, T. K. (1961). The determination of reactor parameters of the Montana State College sub-critical assembly. (Thesis). Montana State University. Retrieved from https://scholarworks.montana.edu/xmlui/handle/1/4956

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):

Chowdhury, Tushar Kumar. “The determination of reactor parameters of the Montana State College sub-critical assembly.” 1961. Thesis, Montana State University. Accessed February 17, 2019. https://scholarworks.montana.edu/xmlui/handle/1/4956.

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

MLA Handbook (7th Edition):

Chowdhury, Tushar Kumar. “The determination of reactor parameters of the Montana State College sub-critical assembly.” 1961. Web. 17 Feb 2019.

Vancouver:

Chowdhury TK. The determination of reactor parameters of the Montana State College sub-critical assembly. [Internet] [Thesis]. Montana State University; 1961. [cited 2019 Feb 17]. Available from: https://scholarworks.montana.edu/xmlui/handle/1/4956.

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

Council of Science Editors:

Chowdhury TK. The determination of reactor parameters of the Montana State College sub-critical assembly. [Thesis]. Montana State University; 1961. Available from: https://scholarworks.montana.edu/xmlui/handle/1/4956

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


Oregon State University

11. Moon, Laurence Leslie. Analysis of nuclear reactor period measurements.

Degree: MS, Electrical Engineering, 1962, Oregon State University

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Moon, L. L. (1962). Analysis of nuclear reactor period measurements. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/49311

Chicago Manual of Style (16th Edition):

Moon, Laurence Leslie. “Analysis of nuclear reactor period measurements.” 1962. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/49311.

MLA Handbook (7th Edition):

Moon, Laurence Leslie. “Analysis of nuclear reactor period measurements.” 1962. Web. 17 Feb 2019.

Vancouver:

Moon LL. Analysis of nuclear reactor period measurements. [Internet] [Masters thesis]. Oregon State University; 1962. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/49311.

Council of Science Editors:

Moon LL. Analysis of nuclear reactor period measurements. [Masters Thesis]. Oregon State University; 1962. Available from: http://hdl.handle.net/1957/49311


Oregon State University

12. Danielson, Jordan J. Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring.

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

 All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing… (more)

Subjects/Keywords: iGrav; Nuclear reactors  – Cooling

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APA (6th Edition):

Danielson, J. J. (2016). Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/60093

Chicago Manual of Style (16th Edition):

Danielson, Jordan J. “Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring.” 2016. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/60093.

MLA Handbook (7th Edition):

Danielson, Jordan J. “Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring.” 2016. Web. 17 Feb 2019.

Vancouver:

Danielson JJ. Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/60093.

Council of Science Editors:

Danielson JJ. Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/60093


Michigan State University

13. Krauss, Frederick G. Activation analysis of the ²⁰⁹Bi (p,2n) reaction.

Degree: MS, Dept. of Physics and Astronomy, 1966, Michigan State University

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Krauss, F. G. (1966). Activation analysis of the ²⁰⁹Bi (p,2n) reaction. (Masters Thesis). Michigan State University. Retrieved from http://etd.lib.msu.edu/islandora/object/etd:11622

Chicago Manual of Style (16th Edition):

Krauss, Frederick G. “Activation analysis of the ²⁰⁹Bi (p,2n) reaction.” 1966. Masters Thesis, Michigan State University. Accessed February 17, 2019. http://etd.lib.msu.edu/islandora/object/etd:11622.

MLA Handbook (7th Edition):

Krauss, Frederick G. “Activation analysis of the ²⁰⁹Bi (p,2n) reaction.” 1966. Web. 17 Feb 2019.

Vancouver:

Krauss FG. Activation analysis of the ²⁰⁹Bi (p,2n) reaction. [Internet] [Masters thesis]. Michigan State University; 1966. [cited 2019 Feb 17]. Available from: http://etd.lib.msu.edu/islandora/object/etd:11622.

Council of Science Editors:

Krauss FG. Activation analysis of the ²⁰⁹Bi (p,2n) reaction. [Masters Thesis]. Michigan State University; 1966. Available from: http://etd.lib.msu.edu/islandora/object/etd:11622


Kansas State University

14. Langford, David Jonathan. Economic considerations in the decommissioning of light water reactors.

Degree: 1974, Kansas State University

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Langford, D. J. (1974). Economic considerations in the decommissioning of light water reactors. (Thesis). Kansas State University. Retrieved from http://hdl.handle.net/2097/11027

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):

Langford, David Jonathan. “Economic considerations in the decommissioning of light water reactors.” 1974. Thesis, Kansas State University. Accessed February 17, 2019. http://hdl.handle.net/2097/11027.

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

MLA Handbook (7th Edition):

Langford, David Jonathan. “Economic considerations in the decommissioning of light water reactors.” 1974. Web. 17 Feb 2019.

Vancouver:

Langford DJ. Economic considerations in the decommissioning of light water reactors. [Internet] [Thesis]. Kansas State University; 1974. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/2097/11027.

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

Council of Science Editors:

Langford DJ. Economic considerations in the decommissioning of light water reactors. [Thesis]. Kansas State University; 1974. Available from: http://hdl.handle.net/2097/11027

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


Michigan State University

15. Emslie, William Arthur. A direct method for the measurement of control rod worth in a nuclear reactor.

Degree: MS, Dept. of Electrical Engineering and Systems Science, 1972, Michigan State University

Subjects/Keywords: Nuclear reactors

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APA (6th Edition):

Emslie, W. A. (1972). A direct method for the measurement of control rod worth in a nuclear reactor. (Masters Thesis). Michigan State University. Retrieved from http://etd.lib.msu.edu/islandora/object/etd:15980

Chicago Manual of Style (16th Edition):

Emslie, William Arthur. “A direct method for the measurement of control rod worth in a nuclear reactor.” 1972. Masters Thesis, Michigan State University. Accessed February 17, 2019. http://etd.lib.msu.edu/islandora/object/etd:15980.

MLA Handbook (7th Edition):

Emslie, William Arthur. “A direct method for the measurement of control rod worth in a nuclear reactor.” 1972. Web. 17 Feb 2019.

Vancouver:

Emslie WA. A direct method for the measurement of control rod worth in a nuclear reactor. [Internet] [Masters thesis]. Michigan State University; 1972. [cited 2019 Feb 17]. Available from: http://etd.lib.msu.edu/islandora/object/etd:15980.

Council of Science Editors:

Emslie WA. A direct method for the measurement of control rod worth in a nuclear reactor. [Masters Thesis]. Michigan State University; 1972. Available from: http://etd.lib.msu.edu/islandora/object/etd:15980


The Ohio State University

16. Carbiener, Wayne Alan. A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection .

Degree: PhD, Graduate School, 1975, The Ohio State University

Subjects/Keywords: Engineering; Nuclear reactors; Nuclear reactors

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APA (6th Edition):

Carbiener, W. A. (1975). A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection . (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1486990930834876

Chicago Manual of Style (16th Edition):

Carbiener, Wayne Alan. “A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection .” 1975. Doctoral Dissertation, The Ohio State University. Accessed February 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1486990930834876.

MLA Handbook (7th Edition):

Carbiener, Wayne Alan. “A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection .” 1975. Web. 17 Feb 2019.

Vancouver:

Carbiener WA. A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection . [Internet] [Doctoral dissertation]. The Ohio State University; 1975. [cited 2019 Feb 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486990930834876.

Council of Science Editors:

Carbiener WA. A theoretical investigation of the quenching of nuclear reactor fuel rods following emergency core coolant injection . [Doctoral Dissertation]. The Ohio State University; 1975. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486990930834876


Ryerson University

17. Puci, Arber. The Heat Transport System in a Heavy Water Nuclear Reactor.

Degree: 2016, Ryerson University

Nuclear power provided 10% of the world's electricity. In Ontario Nuclear provides the base electrical load on the grid. Nuclear power is very unique. It… (more)

Subjects/Keywords: Heat  – Conduction  – Measurement; Heavy water reactors  – Safety measures; Nuclear reactors  – Control; CANDU Reactors  – Safety measures; Nuclear reactors  – Canada  – Safety measures; Nuclear reactors  – Cooling  – Research

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APA (6th Edition):

Puci, A. (2016). The Heat Transport System in a Heavy Water Nuclear Reactor. (Thesis). Ryerson University. Retrieved from https://digital.library.ryerson.ca/islandora/object/RULA%3A4965

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):

Puci, Arber. “The Heat Transport System in a Heavy Water Nuclear Reactor.” 2016. Thesis, Ryerson University. Accessed February 17, 2019. https://digital.library.ryerson.ca/islandora/object/RULA%3A4965.

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

MLA Handbook (7th Edition):

Puci, Arber. “The Heat Transport System in a Heavy Water Nuclear Reactor.” 2016. Web. 17 Feb 2019.

Vancouver:

Puci A. The Heat Transport System in a Heavy Water Nuclear Reactor. [Internet] [Thesis]. Ryerson University; 2016. [cited 2019 Feb 17]. Available from: https://digital.library.ryerson.ca/islandora/object/RULA%3A4965.

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

Council of Science Editors:

Puci A. The Heat Transport System in a Heavy Water Nuclear Reactor. [Thesis]. Ryerson University; 2016. Available from: https://digital.library.ryerson.ca/islandora/object/RULA%3A4965

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


The Ohio State University

18. Webb, Richard E. Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) .

Degree: PhD, Graduate School, 1972, The Ohio State University

Subjects/Keywords: Engineering; Nuclear reactors

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APA (6th Edition):

Webb, R. E. (1972). Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) . (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1486733660882732

Chicago Manual of Style (16th Edition):

Webb, Richard E. “Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) .” 1972. Doctoral Dissertation, The Ohio State University. Accessed February 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1486733660882732.

MLA Handbook (7th Edition):

Webb, Richard E. “Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) .” 1972. Web. 17 Feb 2019.

Vancouver:

Webb RE. Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) . [Internet] [Doctoral dissertation]. The Ohio State University; 1972. [cited 2019 Feb 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486733660882732.

Council of Science Editors:

Webb RE. Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) . [Doctoral Dissertation]. The Ohio State University; 1972. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486733660882732


The Ohio State University

19. Iyer, Shrinivas Shankar. The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure .

Degree: PhD, Graduate School, 1969, The Ohio State University

Subjects/Keywords: Engineering; Nuclear reactors

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APA (6th Edition):

Iyer, S. S. (1969). The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure . (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1486651646497692

Chicago Manual of Style (16th Edition):

Iyer, Shrinivas Shankar. “The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure .” 1969. Doctoral Dissertation, The Ohio State University. Accessed February 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1486651646497692.

MLA Handbook (7th Edition):

Iyer, Shrinivas Shankar. “The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure .” 1969. Web. 17 Feb 2019.

Vancouver:

Iyer SS. The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure . [Internet] [Doctoral dissertation]. The Ohio State University; 1969. [cited 2019 Feb 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486651646497692.

Council of Science Editors:

Iyer SS. The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure . [Doctoral Dissertation]. The Ohio State University; 1969. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486651646497692


The Ohio State University

20. Moon, Kuk Jin. Highly excited states of 12C and 12O from 2He capture studies.

Degree: PhD, Graduate School, 1969, The Ohio State University

Subjects/Keywords: Physics; Nuclear reactors

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APA (6th Edition):

Moon, K. J. (1969). Highly excited states of 12C and 12O from 2He capture studies. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1486655344550106

Chicago Manual of Style (16th Edition):

Moon, Kuk Jin. “Highly excited states of 12C and 12O from 2He capture studies.” 1969. Doctoral Dissertation, The Ohio State University. Accessed February 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1486655344550106.

MLA Handbook (7th Edition):

Moon, Kuk Jin. “Highly excited states of 12C and 12O from 2He capture studies.” 1969. Web. 17 Feb 2019.

Vancouver:

Moon KJ. Highly excited states of 12C and 12O from 2He capture studies. [Internet] [Doctoral dissertation]. The Ohio State University; 1969. [cited 2019 Feb 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486655344550106.

Council of Science Editors:

Moon KJ. Highly excited states of 12C and 12O from 2He capture studies. [Doctoral Dissertation]. The Ohio State University; 1969. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1486655344550106


Texas A&M University

21. Metcalf, Richard R. New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles.

Degree: 2010, Texas A&M University

 The comparison of nuclear facilities based on their barriers to nuclear material proliferation has remained a difficult endeavor, often requiring expert elicitation for each system… (more)

Subjects/Keywords: Nuclear Nonproliferation; Fast Reactors; Proliferation Resistance; Safeguards

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APA (6th Edition):

Metcalf, R. R. (2010). New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-747

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):

Metcalf, Richard R. “New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles.” 2010. Thesis, Texas A&M University. Accessed February 17, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-747.

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

MLA Handbook (7th Edition):

Metcalf, Richard R. “New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles.” 2010. Web. 17 Feb 2019.

Vancouver:

Metcalf RR. New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles. [Internet] [Thesis]. Texas A&M University; 2010. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-747.

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

Council of Science Editors:

Metcalf RR. New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles. [Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-747

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


University of Pretoria

22. Moolman, Francis Sean. A fluidized bed kinetic model for the fluorination of Zircon.

Degree: Chemical Engineering, 2006, University of Pretoria

Please read the abstract in the section 00front of this document Advisors/Committee Members: Mr M D Heydenrych (advisor).

Subjects/Keywords: Nuclear reactors; UCTD

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APA (6th Edition):

Moolman, F. (2006). A fluidized bed kinetic model for the fluorination of Zircon. (Masters Thesis). University of Pretoria. Retrieved from http://hdl.handle.net/2263/30442

Chicago Manual of Style (16th Edition):

Moolman, Francis. “A fluidized bed kinetic model for the fluorination of Zircon.” 2006. Masters Thesis, University of Pretoria. Accessed February 17, 2019. http://hdl.handle.net/2263/30442.

MLA Handbook (7th Edition):

Moolman, Francis. “A fluidized bed kinetic model for the fluorination of Zircon.” 2006. Web. 17 Feb 2019.

Vancouver:

Moolman F. A fluidized bed kinetic model for the fluorination of Zircon. [Internet] [Masters thesis]. University of Pretoria; 2006. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/2263/30442.

Council of Science Editors:

Moolman F. A fluidized bed kinetic model for the fluorination of Zircon. [Masters Thesis]. University of Pretoria; 2006. Available from: http://hdl.handle.net/2263/30442


University of Pretoria

23. [No author]. A fluidized bed kinetic model for the fluorination of Zircon .

Degree: 2006, University of Pretoria

Please read the abstract in the section 00front of this document Advisors/Committee Members: Mr M D Heydenrych (advisor).

Subjects/Keywords: Nuclear reactors; UCTD

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APA (6th Edition):

author], [. (2006). A fluidized bed kinetic model for the fluorination of Zircon . (Masters Thesis). University of Pretoria. Retrieved from http://upetd.up.ac.za/thesis/available/etd-12202006-104822/

Chicago Manual of Style (16th Edition):

author], [No. “A fluidized bed kinetic model for the fluorination of Zircon .” 2006. Masters Thesis, University of Pretoria. Accessed February 17, 2019. http://upetd.up.ac.za/thesis/available/etd-12202006-104822/.

MLA Handbook (7th Edition):

author], [No. “A fluidized bed kinetic model for the fluorination of Zircon .” 2006. Web. 17 Feb 2019.

Vancouver:

author] [. A fluidized bed kinetic model for the fluorination of Zircon . [Internet] [Masters thesis]. University of Pretoria; 2006. [cited 2019 Feb 17]. Available from: http://upetd.up.ac.za/thesis/available/etd-12202006-104822/.

Council of Science Editors:

author] [. A fluidized bed kinetic model for the fluorination of Zircon . [Masters Thesis]. University of Pretoria; 2006. Available from: http://upetd.up.ac.za/thesis/available/etd-12202006-104822/


Oregon State University

24. TenBrook, Warren Kermit. Research reactor coolant monitoring using automated gamma ray spectrometry.

Degree: MS, General Science, 1986, Oregon State University

 An integrated sampling and gamma ray spectrometry system has been developed for analysis of TRIGA reactor primary cooling water. A microcomputer controls pumps and valves… (more)

Subjects/Keywords: Nuclear reactors  – Cooling

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APA (6th Edition):

TenBrook, W. K. (1986). Research reactor coolant monitoring using automated gamma ray spectrometry. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/40112

Chicago Manual of Style (16th Edition):

TenBrook, Warren Kermit. “Research reactor coolant monitoring using automated gamma ray spectrometry.” 1986. Masters Thesis, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/40112.

MLA Handbook (7th Edition):

TenBrook, Warren Kermit. “Research reactor coolant monitoring using automated gamma ray spectrometry.” 1986. Web. 17 Feb 2019.

Vancouver:

TenBrook WK. Research reactor coolant monitoring using automated gamma ray spectrometry. [Internet] [Masters thesis]. Oregon State University; 1986. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/40112.

Council of Science Editors:

TenBrook WK. Research reactor coolant monitoring using automated gamma ray spectrometry. [Masters Thesis]. Oregon State University; 1986. Available from: http://hdl.handle.net/1957/40112


Oregon State University

25. Greek, Kevin J. Development of an object-oriented expert system for PWR core reload.

Degree: PhD, Nuclear Engineering, 1989, Oregon State University

 Reactor refueling is a computationally intensive problem solving process that requires automation since significant resources are expended upon the search for an optimal core loading.… (more)

Subjects/Keywords: Nuclear reactors  – Refueling

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APA (6th Edition):

Greek, K. J. (1989). Development of an object-oriented expert system for PWR core reload. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/38332

Chicago Manual of Style (16th Edition):

Greek, Kevin J. “Development of an object-oriented expert system for PWR core reload.” 1989. Doctoral Dissertation, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/38332.

MLA Handbook (7th Edition):

Greek, Kevin J. “Development of an object-oriented expert system for PWR core reload.” 1989. Web. 17 Feb 2019.

Vancouver:

Greek KJ. Development of an object-oriented expert system for PWR core reload. [Internet] [Doctoral dissertation]. Oregon State University; 1989. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/38332.

Council of Science Editors:

Greek KJ. Development of an object-oriented expert system for PWR core reload. [Doctoral Dissertation]. Oregon State University; 1989. Available from: http://hdl.handle.net/1957/38332


University of Arizona

26. Hlaing, Shwe, 1936-. Prompt neutron lifetime from time dependent thermal diffusion equation .

Degree: 1962, University of Arizona

Subjects/Keywords: Neutrons.; Nuclear reactors.

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APA (6th Edition):

Hlaing, Shwe, 1. (1962). Prompt neutron lifetime from time dependent thermal diffusion equation . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/319409

Chicago Manual of Style (16th Edition):

Hlaing, Shwe, 1936-. “Prompt neutron lifetime from time dependent thermal diffusion equation .” 1962. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/319409.

MLA Handbook (7th Edition):

Hlaing, Shwe, 1936-. “Prompt neutron lifetime from time dependent thermal diffusion equation .” 1962. Web. 17 Feb 2019.

Vancouver:

Hlaing, Shwe 1. Prompt neutron lifetime from time dependent thermal diffusion equation . [Internet] [Masters thesis]. University of Arizona; 1962. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/319409.

Council of Science Editors:

Hlaing, Shwe 1. Prompt neutron lifetime from time dependent thermal diffusion equation . [Masters Thesis]. University of Arizona; 1962. Available from: http://hdl.handle.net/10150/319409


University of Arizona

27. Lewis, Christopher Henry, 1947-. Stability bounds for reactor systems with two feedback mechanisms .

Degree: 1970, University of Arizona

Subjects/Keywords: Nuclear reactors  – Control.

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APA (6th Edition):

Lewis, Christopher Henry, 1. (1970). Stability bounds for reactor systems with two feedback mechanisms . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/318310

Chicago Manual of Style (16th Edition):

Lewis, Christopher Henry, 1947-. “Stability bounds for reactor systems with two feedback mechanisms .” 1970. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/318310.

MLA Handbook (7th Edition):

Lewis, Christopher Henry, 1947-. “Stability bounds for reactor systems with two feedback mechanisms .” 1970. Web. 17 Feb 2019.

Vancouver:

Lewis, Christopher Henry 1. Stability bounds for reactor systems with two feedback mechanisms . [Internet] [Masters thesis]. University of Arizona; 1970. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/318310.

Council of Science Editors:

Lewis, Christopher Henry 1. Stability bounds for reactor systems with two feedback mechanisms . [Masters Thesis]. University of Arizona; 1970. Available from: http://hdl.handle.net/10150/318310


University of Arizona

28. Spear, Richard William, 1942-. Development of the pre-operational test program for the upgraded nuclear reactor .

Degree: 1972, University of Arizona

Subjects/Keywords: Nuclear reactors  – Testing.

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APA (6th Edition):

Spear, Richard William, 1. (1972). Development of the pre-operational test program for the upgraded nuclear reactor . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/554853

Chicago Manual of Style (16th Edition):

Spear, Richard William, 1942-. “Development of the pre-operational test program for the upgraded nuclear reactor .” 1972. Masters Thesis, University of Arizona. Accessed February 17, 2019. http://hdl.handle.net/10150/554853.

MLA Handbook (7th Edition):

Spear, Richard William, 1942-. “Development of the pre-operational test program for the upgraded nuclear reactor .” 1972. Web. 17 Feb 2019.

Vancouver:

Spear, Richard William 1. Development of the pre-operational test program for the upgraded nuclear reactor . [Internet] [Masters thesis]. University of Arizona; 1972. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/10150/554853.

Council of Science Editors:

Spear, Richard William 1. Development of the pre-operational test program for the upgraded nuclear reactor . [Masters Thesis]. University of Arizona; 1972. Available from: http://hdl.handle.net/10150/554853


Oregon State University

29. Luo, Hu. Quantified PIRT and uncertainty quantification for computer code validation.

Degree: PhD, Nuclear Engineering, 2012, Oregon State University

 This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more… (more)

Subjects/Keywords: Code Validation; Nuclear reactors  – Cooling  – Computer simulation

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APA (6th Edition):

Luo, H. (2012). Quantified PIRT and uncertainty quantification for computer code validation. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/35475

Chicago Manual of Style (16th Edition):

Luo, Hu. “Quantified PIRT and uncertainty quantification for computer code validation.” 2012. Doctoral Dissertation, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/35475.

MLA Handbook (7th Edition):

Luo, Hu. “Quantified PIRT and uncertainty quantification for computer code validation.” 2012. Web. 17 Feb 2019.

Vancouver:

Luo H. Quantified PIRT and uncertainty quantification for computer code validation. [Internet] [Doctoral dissertation]. Oregon State University; 2012. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/35475.

Council of Science Editors:

Luo H. Quantified PIRT and uncertainty quantification for computer code validation. [Doctoral Dissertation]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/35475


Oregon State University

30. Skeen, David Roy. Numerical solutions of the neutron transport equation.

Degree: PhD, Mechanical and Nuclear Engineering, 1970, Oregon State University

 Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted accurately. This leads to the high cost computer computations… (more)

Subjects/Keywords: Nuclear reactors  – Refueling

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APA (6th Edition):

Skeen, D. R. (1970). Numerical solutions of the neutron transport equation. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/45543

Chicago Manual of Style (16th Edition):

Skeen, David Roy. “Numerical solutions of the neutron transport equation.” 1970. Doctoral Dissertation, Oregon State University. Accessed February 17, 2019. http://hdl.handle.net/1957/45543.

MLA Handbook (7th Edition):

Skeen, David Roy. “Numerical solutions of the neutron transport equation.” 1970. Web. 17 Feb 2019.

Vancouver:

Skeen DR. Numerical solutions of the neutron transport equation. [Internet] [Doctoral dissertation]. Oregon State University; 1970. [cited 2019 Feb 17]. Available from: http://hdl.handle.net/1957/45543.

Council of Science Editors:

Skeen DR. Numerical solutions of the neutron transport equation. [Doctoral Dissertation]. Oregon State University; 1970. Available from: http://hdl.handle.net/1957/45543

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