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You searched for subject:(spent fuel). Showing records 1 – 30 of 104 total matches.

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University of Illinois – Urbana-Champaign

1. Lartonoix, David. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.

Degree: MS, 5183, 2012, University of Illinois – Urbana-Champaign

 While nuclear reactors in the United States have produced economy-driving power for several decades, they have also left behind a significant amount of spent nuclear… (more)

Subjects/Keywords: spent nuclear fuel; radioisotope inventory

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APA (6th Edition):

Lartonoix, D. (2012). Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/31990

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):

Lartonoix, David. “Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.” 2012. Thesis, University of Illinois – Urbana-Champaign. Accessed March 02, 2021. http://hdl.handle.net/2142/31990.

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

MLA Handbook (7th Edition):

Lartonoix, David. “Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica.” 2012. Web. 02 Mar 2021.

Vancouver:

Lartonoix D. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2012. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/2142/31990.

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

Council of Science Editors:

Lartonoix D. Radioisotope Inventory Of Spent Nuclear Fuel In Mathematica. [Thesis]. University of Illinois – Urbana-Champaign; 2012. Available from: http://hdl.handle.net/2142/31990

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


University of Cape Town

2. Khoza, Best. Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel.

Degree: MPhil, Electrical Engineering, 2019, University of Cape Town

 The continual increase in electricity dependence for the advancement of society has led to increased demand in electricity globally. This increased demand, among other things… (more)

Subjects/Keywords: spent fuel; dry cask storage; spent fuel pool

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APA (6th Edition):

Khoza, B. (2019). Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel. (Thesis). University of Cape Town. Retrieved from http://hdl.handle.net/11427/31697

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):

Khoza, Best. “Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel.” 2019. Thesis, University of Cape Town. Accessed March 02, 2021. http://hdl.handle.net/11427/31697.

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

MLA Handbook (7th Edition):

Khoza, Best. “Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel.” 2019. Web. 02 Mar 2021.

Vancouver:

Khoza B. Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel. [Internet] [Thesis]. University of Cape Town; 2019. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/11427/31697.

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

Council of Science Editors:

Khoza B. Physics and engineering aspects of South Africa's proposed dry storage facility for spent nuclear fuel. [Thesis]. University of Cape Town; 2019. Available from: http://hdl.handle.net/11427/31697

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


Georgia Tech

3. Conant, Andrew. Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The purpose of this research is to examine the effects of systematic uncertainty of reactor operating parameters on isotope ratios in spent fuel rods, specifically… (more)

Subjects/Keywords: Uncertainty; Plutonium; Cesium; Reactor; Spent fuel

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APA (6th Edition):

Conant, A. (2015). Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/56227

Chicago Manual of Style (16th Edition):

Conant, Andrew. “Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod.” 2015. Masters Thesis, Georgia Tech. Accessed March 02, 2021. http://hdl.handle.net/1853/56227.

MLA Handbook (7th Edition):

Conant, Andrew. “Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod.” 2015. Web. 02 Mar 2021.

Vancouver:

Conant A. Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1853/56227.

Council of Science Editors:

Conant A. Sensitivity and uncertainty analysis of plutonium and cesium isotope ratios in BR3 core 4A/B fuel rod. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/56227


University of Illinois – Urbana-Champaign

4. Jarrah, Ibrahim. Risk of misloading spent nuclear fuel cask for light water reactors.

Degree: MS, Nuclear, Plasma, Radiolgc Engr, 2018, University of Illinois – Urbana-Champaign

 The spent fuel dry cask should remain subcritical under normal, abnormal, and accident conditions. The cask may become susceptible to criticality if it is misloaded… (more)

Subjects/Keywords: Spent fuel cask; misload; PRA; Risk

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APA (6th Edition):

Jarrah, I. (2018). Risk of misloading spent nuclear fuel cask for light water reactors. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/102866

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):

Jarrah, Ibrahim. “Risk of misloading spent nuclear fuel cask for light water reactors.” 2018. Thesis, University of Illinois – Urbana-Champaign. Accessed March 02, 2021. http://hdl.handle.net/2142/102866.

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

MLA Handbook (7th Edition):

Jarrah, Ibrahim. “Risk of misloading spent nuclear fuel cask for light water reactors.” 2018. Web. 02 Mar 2021.

Vancouver:

Jarrah I. Risk of misloading spent nuclear fuel cask for light water reactors. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2018. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/2142/102866.

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

Council of Science Editors:

Jarrah I. Risk of misloading spent nuclear fuel cask for light water reactors. [Thesis]. University of Illinois – Urbana-Champaign; 2018. Available from: http://hdl.handle.net/2142/102866

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


Penn State University

5. Bratton, Ryan Nathaniel. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.

Degree: 2015, Penn State University

 The bias and uncertainty in fuel isotopic calculations for a well-defined radiochemical assay benchmark are investigated with Sampler, the new sampling-based uncertainty quantification tool in… (more)

Subjects/Keywords: SCALE; FRAPCON; rod internal pressure; fuel isotopics; spent nuclear fuel

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APA (6th Edition):

Bratton, R. N. (2015). Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27289

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):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Thesis, Penn State University. Accessed March 02, 2021. https://submit-etda.libraries.psu.edu/catalog/27289.

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

MLA Handbook (7th Edition):

Bratton, Ryan Nathaniel. “Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure.” 2015. Web. 02 Mar 2021.

Vancouver:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Mar 02]. Available from: https://submit-etda.libraries.psu.edu/catalog/27289.

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

Council of Science Editors:

Bratton RN. Uncertainty Analysis of Spent Nuclear Fuel Isotopics and Rod Internal Pressure. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27289

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


Texas A&M University

6. Khudoleeva, Alexandra P. Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations.

Degree: MS, Nuclear Engineering, 2013, Texas A&M University

 The International Atomic Energy Agency (IAEA) needs to enhance its capabilities for safeguarding spent nuclear fuel (SNF) stored in dry cask storage facilities and for… (more)

Subjects/Keywords: spent nuclear fuel; dry cask storage; safeguards; remote monitoring system

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APA (6th Edition):

Khudoleeva, A. P. (2013). Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158895

Chicago Manual of Style (16th Edition):

Khudoleeva, Alexandra P. “Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations.” 2013. Masters Thesis, Texas A&M University. Accessed March 02, 2021. http://hdl.handle.net/1969.1/158895.

MLA Handbook (7th Edition):

Khudoleeva, Alexandra P. “Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations.” 2013. Web. 02 Mar 2021.

Vancouver:

Khudoleeva AP. Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1969.1/158895.

Council of Science Editors:

Khudoleeva AP. Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/158895


Uppsala University

7. Lundkvist, Niklas. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.

Degree: Applied Nuclear Physics, 2010, Uppsala University

This report is concerned with the question whether Accelerator mass spectrometry (AMS) is asuitable technique for measuring actinide inventory in spent nuclear fuel, and… (more)

Subjects/Keywords: AMS; actinides; spent; nuclear; fuel

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APA (6th Edition):

Lundkvist, N. (2010). AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011

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):

Lundkvist, Niklas. “AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.” 2010. Thesis, Uppsala University. Accessed March 02, 2021. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011.

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

MLA Handbook (7th Edition):

Lundkvist, Niklas. “AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements.” 2010. Web. 02 Mar 2021.

Vancouver:

Lundkvist N. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. [Internet] [Thesis]. Uppsala University; 2010. [cited 2021 Mar 02]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011.

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

Council of Science Editors:

Lundkvist N. AMS on the actinides in spent nuclear fuel : a study on a technique for inventory measurements. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-130011

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


University of Tennessee – Knoxville

8. Liu, Zhengzhi. METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY.

Degree: 2018, University of Tennessee – Knoxville

 It's important to the International Atomic Energy Agency (IAEA) to develop a nondestructive assay technique that may that be used to verify the presence of… (more)

Subjects/Keywords: Spent nuclear fuel dry storage cask; Muon tomography

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APA (6th Edition):

Liu, Z. (2018). METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/5033

Chicago Manual of Style (16th Edition):

Liu, Zhengzhi. “METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY.” 2018. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed March 02, 2021. https://trace.tennessee.edu/utk_graddiss/5033.

MLA Handbook (7th Edition):

Liu, Zhengzhi. “METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY.” 2018. Web. 02 Mar 2021.

Vancouver:

Liu Z. METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2018. [cited 2021 Mar 02]. Available from: https://trace.tennessee.edu/utk_graddiss/5033.

Council of Science Editors:

Liu Z. METHODOLOGIES FOR IMAGING A USED NUCLEAR FUEL DRY STORAGE CASK WITH COSMIC RAY MUON COMPUTED TOMOGRAPHY. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2018. Available from: https://trace.tennessee.edu/utk_graddiss/5033


University of Tennessee – Knoxville

9. Iyengar, Anagha Srikanth. The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography.

Degree: 2019, University of Tennessee – Knoxville

 Safeguarding spent fuel in spent fuel pools, during transportation, and at dry cask storage sites has been a continuing priority for the International Atomic Energy… (more)

Subjects/Keywords: International Safeguards; Spent Fuel; Fast Neutrons; Imaging; Tomography

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APA (6th Edition):

Iyengar, A. S. (2019). The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/5343

Chicago Manual of Style (16th Edition):

Iyengar, Anagha Srikanth. “The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography.” 2019. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed March 02, 2021. https://trace.tennessee.edu/utk_graddiss/5343.

MLA Handbook (7th Edition):

Iyengar, Anagha Srikanth. “The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography.” 2019. Web. 02 Mar 2021.

Vancouver:

Iyengar AS. The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2019. [cited 2021 Mar 02]. Available from: https://trace.tennessee.edu/utk_graddiss/5343.

Council of Science Editors:

Iyengar AS. The Design of an Imager to Safeguard Spent Fuel Using Passive Fast Neutron Emission Tomography. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2019. Available from: https://trace.tennessee.edu/utk_graddiss/5343

10. Wikman, Tom. Analysis of Loss of Cooling in Spent Nuclear Fuel Pools .

Degree: Chalmers tekniska högskola / Institutionen för fysik, 2019, Chalmers University of Technology

 This master thesis presents an improved estimate of the course of events in the loss of cooling of the spent fuel pools on Ringhals 3… (more)

Subjects/Keywords: Ringhals; loss of cooling; spent fuel pool; evaporation; Comsol Multiphysics

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APA (6th Edition):

Wikman, T. (2019). Analysis of Loss of Cooling in Spent Nuclear Fuel Pools . (Thesis). Chalmers University of Technology. Retrieved from http://hdl.handle.net/20.500.12380/300378

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):

Wikman, Tom. “Analysis of Loss of Cooling in Spent Nuclear Fuel Pools .” 2019. Thesis, Chalmers University of Technology. Accessed March 02, 2021. http://hdl.handle.net/20.500.12380/300378.

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

MLA Handbook (7th Edition):

Wikman, Tom. “Analysis of Loss of Cooling in Spent Nuclear Fuel Pools .” 2019. Web. 02 Mar 2021.

Vancouver:

Wikman T. Analysis of Loss of Cooling in Spent Nuclear Fuel Pools . [Internet] [Thesis]. Chalmers University of Technology; 2019. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/20.500.12380/300378.

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

Council of Science Editors:

Wikman T. Analysis of Loss of Cooling in Spent Nuclear Fuel Pools . [Thesis]. Chalmers University of Technology; 2019. Available from: http://hdl.handle.net/20.500.12380/300378

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


Virginia Tech

11. Roskoff, Nathan. Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation.

Degree: PhD, Nuclear Engineering, 2018, Virginia Tech

Fuel burnup calculations provide material concentrations and intrinsic neutron and gamma source strengths as a function of irradiation and cooling time. Detailed, full-core 3D burnup… (more)

Subjects/Keywords: burnup; depletion; neutron transport; spent nuclear fuel; fission matrix; RAPID

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APA (6th Edition):

Roskoff, N. (2018). Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/84487

Chicago Manual of Style (16th Edition):

Roskoff, Nathan. “Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation.” 2018. Doctoral Dissertation, Virginia Tech. Accessed March 02, 2021. http://hdl.handle.net/10919/84487.

MLA Handbook (7th Edition):

Roskoff, Nathan. “Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation.” 2018. Web. 02 Mar 2021.

Vancouver:

Roskoff N. Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation. [Internet] [Doctoral dissertation]. Virginia Tech; 2018. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/10919/84487.

Council of Science Editors:

Roskoff N. Development of a Novel Fuel Burnup Methodology and Algorithm in RAPID and its Benchmarking and Automation. [Doctoral Dissertation]. Virginia Tech; 2018. Available from: http://hdl.handle.net/10919/84487


Vanderbilt University

12. Favret, Derek Joe. Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities.

Degree: MS, Physics, 2006, Vanderbilt University

 Since September 11, 2001, the safety and security of the U.S. nuclear reactor complex has become a topic of controversy. Due to the safety features… (more)

Subjects/Keywords: terrorist; spent; nuclear; fuel; storage

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APA (6th Edition):

Favret, D. J. (2006). Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities. (Thesis). Vanderbilt University. Retrieved from http://hdl.handle.net/1803/13360

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):

Favret, Derek Joe. “Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities.” 2006. Thesis, Vanderbilt University. Accessed March 02, 2021. http://hdl.handle.net/1803/13360.

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

MLA Handbook (7th Edition):

Favret, Derek Joe. “Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities.” 2006. Web. 02 Mar 2021.

Vancouver:

Favret DJ. Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities. [Internet] [Thesis]. Vanderbilt University; 2006. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1803/13360.

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

Council of Science Editors:

Favret DJ. Analysis on the Potential Implications of a Terrorist Attack at U.S. Spent Nuclear Fuel Storage Facilities. [Thesis]. Vanderbilt University; 2006. Available from: http://hdl.handle.net/1803/13360

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


Purdue University

13. Chatzidakis, Stylianos. Cosmic ray muons for spent nuclear fuel monitoring.

Degree: PhD, Nuclear Engineering, 2016, Purdue University

  There is a steady increase in the volume of spent nuclear fuel stored on-site (at reactor) as currently there is no permanent disposal option.… (more)

Subjects/Keywords: Applied sciences; Cosmic ray muons; Spent nuclear fuel; Nuclear Engineering

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APA (6th Edition):

Chatzidakis, S. (2016). Cosmic ray muons for spent nuclear fuel monitoring. (Doctoral Dissertation). Purdue University. Retrieved from https://docs.lib.purdue.edu/open_access_dissertations/631

Chicago Manual of Style (16th Edition):

Chatzidakis, Stylianos. “Cosmic ray muons for spent nuclear fuel monitoring.” 2016. Doctoral Dissertation, Purdue University. Accessed March 02, 2021. https://docs.lib.purdue.edu/open_access_dissertations/631.

MLA Handbook (7th Edition):

Chatzidakis, Stylianos. “Cosmic ray muons for spent nuclear fuel monitoring.” 2016. Web. 02 Mar 2021.

Vancouver:

Chatzidakis S. Cosmic ray muons for spent nuclear fuel monitoring. [Internet] [Doctoral dissertation]. Purdue University; 2016. [cited 2021 Mar 02]. Available from: https://docs.lib.purdue.edu/open_access_dissertations/631.

Council of Science Editors:

Chatzidakis S. Cosmic ray muons for spent nuclear fuel monitoring. [Doctoral Dissertation]. Purdue University; 2016. Available from: https://docs.lib.purdue.edu/open_access_dissertations/631

14. Alam, Md Hasibul. ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process.

Degree: 2016, University of Nevada – Reno

 This thesis describes the development and design of simulation model in “ANSYS FLUENT” for Spent Nuclear Fuel dehydration process by “Forced Helium Dehydration” [13] method… (more)

Subjects/Keywords: Forced Helium Dehydration; Nuclear Waste Management; Spent Nuclear Fuel Drying

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APA (6th Edition):

Alam, M. H. (2016). ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process. (Thesis). University of Nevada – Reno. Retrieved from http://hdl.handle.net/11714/2117

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):

Alam, Md Hasibul. “ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process.” 2016. Thesis, University of Nevada – Reno. Accessed March 02, 2021. http://hdl.handle.net/11714/2117.

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

MLA Handbook (7th Edition):

Alam, Md Hasibul. “ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process.” 2016. Web. 02 Mar 2021.

Vancouver:

Alam MH. ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process. [Internet] [Thesis]. University of Nevada – Reno; 2016. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/11714/2117.

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

Council of Science Editors:

Alam MH. ANSYS/Fluent Simulation Model Development for Forced Helium Dehydration Process. [Thesis]. University of Nevada – Reno; 2016. Available from: http://hdl.handle.net/11714/2117

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


Texas A&M University

15. Yancey, Kristina. Nationwide Used Fuel Inventory Analysis.

Degree: MS, Nuclear Engineering, 2013, Texas A&M University

 The goal of this research was to develop a methodology to collect inventory estimates for the analysis and characterization of used fuel in the United… (more)

Subjects/Keywords: nuclear; energy; spent fuel; used fuel; nuclide inventories; PWR; BWR; applicability range

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APA (6th Edition):

Yancey, K. (2013). Nationwide Used Fuel Inventory Analysis. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151866

Chicago Manual of Style (16th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Masters Thesis, Texas A&M University. Accessed March 02, 2021. http://hdl.handle.net/1969.1/151866.

MLA Handbook (7th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Web. 02 Mar 2021.

Vancouver:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1969.1/151866.

Council of Science Editors:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151866

16. Gullekson, Brian J. Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases.

Degree: MS, Nuclear Engineering, 2013, Oregon State University

Spent nuclear fuel (SNF) resultant from the generation of nuclear power is a chemically and radiologically diverse system which is advantageous to chemically process prior… (more)

Subjects/Keywords: Spent Nuclear Fuel Reprocessing; Spent reactor fuels

…1 Spent Nuclear Fuel Characterization ….. ….1 I.2 Liquid-Liquid Extraction… …Principles ….3 I.3 Spent Nuclear Fuel Reprocessing .6 I.4 Hard-Soft… …81 I. Problem Background and Experimental Approach I.1 Spent Nuclear Fuel… …precious metals from spent nuclear fuel reprocessing waste streams. Nuclear fission is the only… …MWd/MT at 150 days after discharge, the spent fuel contains 95.9% uranium, 1.0% minor… 

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APA (6th Edition):

Gullekson, B. J. (2013). Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/37706

Chicago Manual of Style (16th Edition):

Gullekson, Brian J. “Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases.” 2013. Masters Thesis, Oregon State University. Accessed March 02, 2021. http://hdl.handle.net/1957/37706.

MLA Handbook (7th Edition):

Gullekson, Brian J. “Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases.” 2013. Web. 02 Mar 2021.

Vancouver:

Gullekson BJ. Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases. [Internet] [Masters thesis]. Oregon State University; 2013. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1957/37706.

Council of Science Editors:

Gullekson BJ. Synthesis and testing of a novel soft donor organic extractant molecule for targeted soft metal extraction from aqueous phases. [Masters Thesis]. Oregon State University; 2013. Available from: http://hdl.handle.net/1957/37706


University of Tennessee – Knoxville

17. Petersen, Gordon Matthew. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.

Degree: 2016, University of Tennessee – Knoxville

 Commercial nuclear power plants produce long-lasting nuclear waste, primarily in the form of spent nuclear fuel (SNF) assemblies. Spent fuel pools (SFP) and canisters or… (more)

Subjects/Keywords: Optimization; Spent Nuclear Fuel; Allocation Strategy; Fuel Removal; Used Nuclear Fuel; Tractable Validation Model; Nuclear Engineering

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APA (6th Edition):

Petersen, G. M. (2016). Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/4156

Chicago Manual of Style (16th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed March 02, 2021. https://trace.tennessee.edu/utk_graddiss/4156.

MLA Handbook (7th Edition):

Petersen, Gordon Matthew. “Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy.” 2016. Web. 02 Mar 2021.

Vancouver:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2016. [cited 2021 Mar 02]. Available from: https://trace.tennessee.edu/utk_graddiss/4156.

Council of Science Editors:

Petersen GM. Algorithms and Methods for Optimizing the Spent Nuclear Fuel Allocation Strategy. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_graddiss/4156


Brno University of Technology

18. Marcell, Jan. Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment.

Degree: 2019, Brno University of Technology

 The main object of this diploma thesis is solving problems concerning heat transfer in disposal cannister for spent nuclear fuel. In forepart possibilities of conceptual… (more)

Subjects/Keywords: úložný obalový soubor; hlubinné úložiště; vyhořelé jaderné palivo; přestup tepla; analytická metoda; numerická metoda; spent fuel cask; deep repository; spent fuel; heat transfer; analytical method; numerical method

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APA (6th Edition):

Marcell, J. (2019). Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/12194

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):

Marcell, Jan. “Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment.” 2019. Thesis, Brno University of Technology. Accessed March 02, 2021. http://hdl.handle.net/11012/12194.

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

MLA Handbook (7th Edition):

Marcell, Jan. “Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment.” 2019. Web. 02 Mar 2021.

Vancouver:

Marcell J. Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/11012/12194.

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

Council of Science Editors:

Marcell J. Přenos tepla v úložném obalovém souboru a jeho vliv na okolí: Heat transfer in the storage cask and its impact on the environment. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/12194

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


University of Guelph

19. AL-Kaabi, Zainab. Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor.

Degree: PhD, 2020, University of Guelph

 One of the strategies of the circular economy is the utilization of organic byproducts by converting them to renewable bio-fuel and bio-materials. Adoption of this… (more)

Subjects/Keywords: bio-carbon; bio-fuel; hydrogen peroxide; oxidation; recycled paper; spent liquor; bio-carbon; bio-fuel; hydrogen peroxide; oxidation; recycled paper; spent liquor

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

APA (6th Edition):

AL-Kaabi, Z. (2020). Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor. (Doctoral Dissertation). University of Guelph. Retrieved from https://atrium.lib.uoguelph.ca/xmlui/handle/10214/17722

Chicago Manual of Style (16th Edition):

AL-Kaabi, Zainab. “Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor.” 2020. Doctoral Dissertation, University of Guelph. Accessed March 02, 2021. https://atrium.lib.uoguelph.ca/xmlui/handle/10214/17722.

MLA Handbook (7th Edition):

AL-Kaabi, Zainab. “Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor.” 2020. Web. 02 Mar 2021.

Vancouver:

AL-Kaabi Z. Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor. [Internet] [Doctoral dissertation]. University of Guelph; 2020. [cited 2021 Mar 02]. Available from: https://atrium.lib.uoguelph.ca/xmlui/handle/10214/17722.

Council of Science Editors:

AL-Kaabi Z. Bio-carbon Production from Recycled Paper Neutral Sulphite Semi-chemical Spent Liquor. [Doctoral Dissertation]. University of Guelph; 2020. Available from: https://atrium.lib.uoguelph.ca/xmlui/handle/10214/17722


University of California – Berkeley

20. Mozin, Vladimir. Delayed Gamma-Ray Assay for Nuclear Safeguards.

Degree: Nuclear Engineering, 2011, University of California – Berkeley

 This dissertation addresses the need for new non-destructive assay instruments capable of quantifying the fissile isotopic composition of spent nuclear fuel and of independently verifying… (more)

Subjects/Keywords: Nuclear engineering; delayed gamma-ray assay; non-destructive assay; nuclear safeguards; spent nuclear fuel

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APA (6th Edition):

Mozin, V. (2011). Delayed Gamma-Ray Assay for Nuclear Safeguards. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/5mm1v58k

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):

Mozin, Vladimir. “Delayed Gamma-Ray Assay for Nuclear Safeguards.” 2011. Thesis, University of California – Berkeley. Accessed March 02, 2021. http://www.escholarship.org/uc/item/5mm1v58k.

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

MLA Handbook (7th Edition):

Mozin, Vladimir. “Delayed Gamma-Ray Assay for Nuclear Safeguards.” 2011. Web. 02 Mar 2021.

Vancouver:

Mozin V. Delayed Gamma-Ray Assay for Nuclear Safeguards. [Internet] [Thesis]. University of California – Berkeley; 2011. [cited 2021 Mar 02]. Available from: http://www.escholarship.org/uc/item/5mm1v58k.

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

Council of Science Editors:

Mozin V. Delayed Gamma-Ray Assay for Nuclear Safeguards. [Thesis]. University of California – Berkeley; 2011. Available from: http://www.escholarship.org/uc/item/5mm1v58k

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


Texas A&M University

21. Goodsell, Alison. Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 The ability to quickly and accurately quantify the plutonium (Pu) content in pressurized water reactor (PWR) spent nuclear fuel (SNF) is critical for nuclear forensics… (more)

Subjects/Keywords: x-ray fluorescence; Pu; U; nuclear forensics; spent nuclear fuel; crystal x-ray spectrometer

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APA (6th Edition):

Goodsell, A. (2012). Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11627

Chicago Manual of Style (16th Edition):

Goodsell, Alison. “Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications.” 2012. Masters Thesis, Texas A&M University. Accessed March 02, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11627.

MLA Handbook (7th Edition):

Goodsell, Alison. “Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications.” 2012. Web. 02 Mar 2021.

Vancouver:

Goodsell A. Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11627.

Council of Science Editors:

Goodsell A. Flat Quartz-Crystal X-ray Spectrometer for Nuclear Forensics Applications. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11627


Texas A&M University

22. Gerhart, Jeremy Jens. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.

Degree: MS, Nuclear Engineering, 2015, Texas A&M University

 There is a need for a technique that is able to quickly and accurately quantify the amount of 239Pu in spent nuclear fuel. With the… (more)

Subjects/Keywords: nuclear; resonance; fluorescence; nrf; cog; plutonium; mega-ray; spent fuel; pressurized water reactor; pwr

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APA (6th Edition):

Gerhart, J. J. (2015). Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156269

Chicago Manual of Style (16th Edition):

Gerhart, Jeremy Jens. “Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.” 2015. Masters Thesis, Texas A&M University. Accessed March 02, 2021. http://hdl.handle.net/1969.1/156269.

MLA Handbook (7th Edition):

Gerhart, Jeremy Jens. “Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel.” 2015. Web. 02 Mar 2021.

Vancouver:

Gerhart JJ. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. [Internet] [Masters thesis]. Texas A&M University; 2015. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1969.1/156269.

Council of Science Editors:

Gerhart JJ. Simulation of Nuclear Resonance Fluorescence for the Quantification of Plutonium-239 in Nuclear Fuel. [Masters Thesis]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/156269


Texas A&M University

23. Eigenbrodt, Julia M. Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

 The International Atomic Energy Agency’s (IAEA) safeguards technical objective is the timely detection of a diversion of a significant quantity of nuclear material from peaceful… (more)

Subjects/Keywords: PNAR; NDA; safeguards; nuclear engineering; spent nuclear fuel; photon measurements; neutron measurements

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APA (6th Edition):

Eigenbrodt, J. M. (2016). Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/156845

Chicago Manual of Style (16th Edition):

Eigenbrodt, Julia M. “Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures.” 2016. Doctoral Dissertation, Texas A&M University. Accessed March 02, 2021. http://hdl.handle.net/1969.1/156845.

MLA Handbook (7th Edition):

Eigenbrodt, Julia M. “Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures.” 2016. Web. 02 Mar 2021.

Vancouver:

Eigenbrodt JM. Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/1969.1/156845.

Council of Science Editors:

Eigenbrodt JM. Spent Fuel Measurements: Passive Neutron Albedo Reactivity (PNAR) and Photon Signatures. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/156845


Penn State University

24. Bender, Sarah Elizabeth. Study of Compton Suppression For Use in Spent Nuclear Fuel Assay.

Degree: 2014, Penn State University

 Nuclear material accountancy is of continuous concern for the regulatory, safeguards, and verification communities. In particular, spent nuclear fuel reprocessing facilities pose one of the… (more)

Subjects/Keywords: Spent fuel; Compton suppression; gamma spectroscopy; lanthanum bromide; burnup; Monte Carlo; Geant4

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APA (6th Edition):

Bender, S. E. (2014). Study of Compton Suppression For Use in Spent Nuclear Fuel Assay. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/21088

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):

Bender, Sarah Elizabeth. “Study of Compton Suppression For Use in Spent Nuclear Fuel Assay.” 2014. Thesis, Penn State University. Accessed March 02, 2021. https://submit-etda.libraries.psu.edu/catalog/21088.

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

MLA Handbook (7th Edition):

Bender, Sarah Elizabeth. “Study of Compton Suppression For Use in Spent Nuclear Fuel Assay.” 2014. Web. 02 Mar 2021.

Vancouver:

Bender SE. Study of Compton Suppression For Use in Spent Nuclear Fuel Assay. [Internet] [Thesis]. Penn State University; 2014. [cited 2021 Mar 02]. Available from: https://submit-etda.libraries.psu.edu/catalog/21088.

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

Council of Science Editors:

Bender SE. Study of Compton Suppression For Use in Spent Nuclear Fuel Assay. [Thesis]. Penn State University; 2014. Available from: https://submit-etda.libraries.psu.edu/catalog/21088

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


North Carolina State University

25. Bobolea, Ruxandra. A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel.

Degree: MS, Nuclear Engineering, 2009, North Carolina State University

 Several methods of reprocessing are currently available to separate recyclable materials from spent nuclear fuel. Electrochemical processing, also known as pyroprocessing, represents a non-aqueous method… (more)

Subjects/Keywords: diffusion layer thickness; continuous reprocessing; electrochemical processing; spent nuclear fuel; pyroprocessing; electrorefiner

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APA (6th Edition):

Bobolea, R. (2009). A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel. (Thesis). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/738

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):

Bobolea, Ruxandra. “A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel.” 2009. Thesis, North Carolina State University. Accessed March 02, 2021. http://www.lib.ncsu.edu/resolver/1840.16/738.

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

MLA Handbook (7th Edition):

Bobolea, Ruxandra. “A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel.” 2009. Web. 02 Mar 2021.

Vancouver:

Bobolea R. A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel. [Internet] [Thesis]. North Carolina State University; 2009. [cited 2021 Mar 02]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/738.

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

Council of Science Editors:

Bobolea R. A Study of Continuous Electrochemical Processing Operation Feasibility for Spent Nuclear Fuel. [Thesis]. North Carolina State University; 2009. Available from: http://www.lib.ncsu.edu/resolver/1840.16/738

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


University of Manchester

26. Foster, Lynn. Understanding the microbial ecology of highly radioactive nuclear storage facilities.

Degree: 2019, University of Manchester

 The First Generation Magnox Storage Pond (FGMSP) is situated on the Sellafield Ltd site in the UK, and is an extremely inhospitable environment comprising of… (more)

Subjects/Keywords: First Generation Magnox Storage Pond; Peudanabaena; Radioactivity; Spent nuclear fuel ponds; Cyanobacteria

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APA (6th Edition):

Foster, L. (2019). Understanding the microbial ecology of highly radioactive nuclear storage facilities. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:318101

Chicago Manual of Style (16th Edition):

Foster, Lynn. “Understanding the microbial ecology of highly radioactive nuclear storage facilities.” 2019. Doctoral Dissertation, University of Manchester. Accessed March 02, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:318101.

MLA Handbook (7th Edition):

Foster, Lynn. “Understanding the microbial ecology of highly radioactive nuclear storage facilities.” 2019. Web. 02 Mar 2021.

Vancouver:

Foster L. Understanding the microbial ecology of highly radioactive nuclear storage facilities. [Internet] [Doctoral dissertation]. University of Manchester; 2019. [cited 2021 Mar 02]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:318101.

Council of Science Editors:

Foster L. Understanding the microbial ecology of highly radioactive nuclear storage facilities. [Doctoral Dissertation]. University of Manchester; 2019. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:318101


University of Colorado

27. Jing, Yuxiang. Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants.

Degree: PhD, 2018, University of Colorado

 To ensure safe operation of nuclear power plants (NPPs) during their service life and enhance the performance of spent nuclear fuel (SNF) storage systems, comprehensive… (more)

Subjects/Keywords: spent nuclear fuel; neutron radiation; concrete; nuclear power plants; deterioration; Civil Engineering; Nuclear

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APA (6th Edition):

Jing, Y. (2018). Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants. (Doctoral Dissertation). University of Colorado. Retrieved from https://scholar.colorado.edu/cven_gradetds/360

Chicago Manual of Style (16th Edition):

Jing, Yuxiang. “Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants.” 2018. Doctoral Dissertation, University of Colorado. Accessed March 02, 2021. https://scholar.colorado.edu/cven_gradetds/360.

MLA Handbook (7th Edition):

Jing, Yuxiang. “Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants.” 2018. Web. 02 Mar 2021.

Vancouver:

Jing Y. Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants. [Internet] [Doctoral dissertation]. University of Colorado; 2018. [cited 2021 Mar 02]. Available from: https://scholar.colorado.edu/cven_gradetds/360.

Council of Science Editors:

Jing Y. Deterioration of Multi-Functional Cementitious Materials in Nuclear Power Plants. [Doctoral Dissertation]. University of Colorado; 2018. Available from: https://scholar.colorado.edu/cven_gradetds/360


Virginia Tech

28. Hor, Yuenkeung. The Daya Bay Reactor Neutrino Experiment.

Degree: PhD, Physics, 2014, Virginia Tech

 The Daya Bay experiment has determined the last unknown mixing angle θ13. This thesis describes the layout of the experiment and the detector design. The… (more)

Subjects/Keywords: muon veto; anti-neutrino detector; attenuation length; spent fuel neutrino; reactor spectrum

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APA (6th Edition):

Hor, Y. (2014). The Daya Bay Reactor Neutrino Experiment. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/50523

Chicago Manual of Style (16th Edition):

Hor, Yuenkeung. “The Daya Bay Reactor Neutrino Experiment.” 2014. Doctoral Dissertation, Virginia Tech. Accessed March 02, 2021. http://hdl.handle.net/10919/50523.

MLA Handbook (7th Edition):

Hor, Yuenkeung. “The Daya Bay Reactor Neutrino Experiment.” 2014. Web. 02 Mar 2021.

Vancouver:

Hor Y. The Daya Bay Reactor Neutrino Experiment. [Internet] [Doctoral dissertation]. Virginia Tech; 2014. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/10919/50523.

Council of Science Editors:

Hor Y. The Daya Bay Reactor Neutrino Experiment. [Doctoral Dissertation]. Virginia Tech; 2014. Available from: http://hdl.handle.net/10919/50523


Brno University of Technology

29. Hlatký, Pavel. Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation.

Degree: 2019, Brno University of Technology

 This work deals with questions of spent fuel storage casks thermal and physical properties investigation. Foundations of mathematics which are necessary for describing field of… (more)

Subjects/Keywords: Přenos tepla; použití jaderné palivo; skladovací kontejner.; Heat transfer; spent nuclear fuel; storage cask.

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

APA (6th Edition):

Hlatký, P. (2019). Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/17616

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):

Hlatký, Pavel. “Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation.” 2019. Thesis, Brno University of Technology. Accessed March 02, 2021. http://hdl.handle.net/11012/17616.

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

MLA Handbook (7th Edition):

Hlatký, Pavel. “Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation.” 2019. Web. 02 Mar 2021.

Vancouver:

Hlatký P. Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Mar 02]. Available from: http://hdl.handle.net/11012/17616.

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

Council of Science Editors:

Hlatký P. Studium tepelných a fyzikálních vlastností skladovacích kontejnerů pro použité jaderné palivo: Spent fuel storage casks thermal and physical properties investigation. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/17616

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


University of Manchester

30. Foster, Lynn. Understanding the microbial ecology of highly radioactive nuclear storage facilities.

Degree: PhD, 2019, University of Manchester

 The First Generation Magnox Storage Pond (FGMSP) is situated on the Sellafield Ltd site in the UK, and is an extremely inhospitable environment comprising of… (more)

Subjects/Keywords: Cyanobacteria; First Generation Magnox Storage Pond; Peudanabaena; Radioactivity; Spent nuclear fuel ponds

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

APA (6th Edition):

Foster, L. (2019). Understanding the microbial ecology of highly radioactive nuclear storage facilities. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/understanding-the-microbial-ecology-of-highly-radioactive-nuclear-storage-facilities(fcac8152-dbec-4260-ac8c-08f4580e0736).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.799458

Chicago Manual of Style (16th Edition):

Foster, Lynn. “Understanding the microbial ecology of highly radioactive nuclear storage facilities.” 2019. Doctoral Dissertation, University of Manchester. Accessed March 02, 2021. https://www.research.manchester.ac.uk/portal/en/theses/understanding-the-microbial-ecology-of-highly-radioactive-nuclear-storage-facilities(fcac8152-dbec-4260-ac8c-08f4580e0736).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.799458.

MLA Handbook (7th Edition):

Foster, Lynn. “Understanding the microbial ecology of highly radioactive nuclear storage facilities.” 2019. Web. 02 Mar 2021.

Vancouver:

Foster L. Understanding the microbial ecology of highly radioactive nuclear storage facilities. [Internet] [Doctoral dissertation]. University of Manchester; 2019. [cited 2021 Mar 02]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/understanding-the-microbial-ecology-of-highly-radioactive-nuclear-storage-facilities(fcac8152-dbec-4260-ac8c-08f4580e0736).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.799458.

Council of Science Editors:

Foster L. Understanding the microbial ecology of highly radioactive nuclear storage facilities. [Doctoral Dissertation]. University of Manchester; 2019. Available from: https://www.research.manchester.ac.uk/portal/en/theses/understanding-the-microbial-ecology-of-highly-radioactive-nuclear-storage-facilities(fcac8152-dbec-4260-ac8c-08f4580e0736).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.799458

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