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You searched for subject:(dry storage cask). Showing records 1 – 15 of 15 total matches.

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Texas A&M University

1. Kelly, Ryan Patrick. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.

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

 The objective of this thesis is to quantify the uncertainty in radiation dose rate estimates outside of a used fuel dry cask storage unit due… (more)

Subjects/Keywords: concrete; shielding; composition; dry cask storage

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APA (6th Edition):

Kelly, R. P. (2013). Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/158896

Chicago Manual of Style (16th Edition):

Kelly, Ryan Patrick. “Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.” 2013. Masters Thesis, Texas A&M University. Accessed March 08, 2021. http://hdl.handle.net/1969.1/158896.

MLA Handbook (7th Edition):

Kelly, Ryan Patrick. “Uncertainty Quantification of Concrete Utilized in Dry Cask Storage.” 2013. Web. 08 Mar 2021.

Vancouver:

Kelly RP. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/1969.1/158896.

Council of Science Editors:

Kelly RP. Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/158896


Texas A&M University

2. 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 08, 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. 08 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 08]. 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


University of Tennessee – Knoxville

3. 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 08, 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. 08 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 08]. 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 Cape Town

4. 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 08, 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. 08 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 08]. 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


Penn State University

5. Mcnelly, Brendan P. Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints.

Degree: 2015, Penn State University

 The goal of this thesis is to design a structurally- and environmentally-constrained, tethered and semi-autonomous robot that is able to inspect the interior crawl space… (more)

Subjects/Keywords: robotic design; nuclear inspection; dry storage cask; wedging and jamming; peg insertion; thermal constraints

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APA (6th Edition):

Mcnelly, B. P. (2015). Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27409

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):

Mcnelly, Brendan P. “Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints.” 2015. Thesis, Penn State University. Accessed March 08, 2021. https://submit-etda.libraries.psu.edu/catalog/27409.

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

MLA Handbook (7th Edition):

Mcnelly, Brendan P. “Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints.” 2015. Web. 08 Mar 2021.

Vancouver:

Mcnelly BP. Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Mar 08]. Available from: https://submit-etda.libraries.psu.edu/catalog/27409.

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

Council of Science Editors:

Mcnelly BP. Design of a Nuclear Inspection Robot: Considering Dimensional, Force, Sensor Packaging, and Thermal Constraints. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27409

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


University of Houston

6. -3679-2535. Crash Analysis of Degraded Concrete Containment Structures.

Degree: PhD, Civil Engineering, 2017, University of Houston

Dry storage casks are composite structures made of an inner steel liner and a concrete outerpack that houses the basket of the spent nuclear fuel… (more)

Subjects/Keywords: Dry cask storage; Creep; Shrinkage; Heat transfer; Moisture transfer; Alkali-Silica Reaction (ASR); Tip-over

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APA (6th Edition):

-3679-2535. (2017). Crash Analysis of Degraded Concrete Containment Structures. (Doctoral Dissertation). University of Houston. Retrieved from http://hdl.handle.net/10657/4822

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Chicago Manual of Style (16th Edition):

-3679-2535. “Crash Analysis of Degraded Concrete Containment Structures.” 2017. Doctoral Dissertation, University of Houston. Accessed March 08, 2021. http://hdl.handle.net/10657/4822.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

MLA Handbook (7th Edition):

-3679-2535. “Crash Analysis of Degraded Concrete Containment Structures.” 2017. Web. 08 Mar 2021.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Vancouver:

-3679-2535. Crash Analysis of Degraded Concrete Containment Structures. [Internet] [Doctoral dissertation]. University of Houston; 2017. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/10657/4822.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Council of Science Editors:

-3679-2535. Crash Analysis of Degraded Concrete Containment Structures. [Doctoral Dissertation]. University of Houston; 2017. Available from: http://hdl.handle.net/10657/4822

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete


University of Houston

7. -5414-1461. Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks.

Degree: PhD, Civil Engineering, 2016, University of Houston

 The durability is one of the main reasons making concrete the most abundantly consumed material in the world after water. However, severe exposure conditions and… (more)

Subjects/Keywords: ASR; Corrosion; Concrete; Aging; Dry cask storage; Service Life; Destructive Testing; Non-Destructive Testing

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APA (6th Edition):

-5414-1461. (2016). Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks. (Doctoral Dissertation). University of Houston. Retrieved from http://hdl.handle.net/10657/5383

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Chicago Manual of Style (16th Edition):

-5414-1461. “Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks.” 2016. Doctoral Dissertation, University of Houston. Accessed March 08, 2021. http://hdl.handle.net/10657/5383.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

MLA Handbook (7th Edition):

-5414-1461. “Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks.” 2016. Web. 08 Mar 2021.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Vancouver:

-5414-1461. Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks. [Internet] [Doctoral dissertation]. University of Houston; 2016. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/10657/5383.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Council of Science Editors:

-5414-1461. Accelerated Alkali-Silica Reaction and Corrosion of Reinforcing Steel in Concrete: Application on Dry Casks. [Doctoral Dissertation]. University of Houston; 2016. Available from: http://hdl.handle.net/10657/5383

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete


Penn State University

8. Cinbiz, Mahmut Nedim. THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION.

Degree: 2015, Penn State University

 Prior to storage in a dry-cask facility, spent nuclear fuel must undergo a vacuum drying cycle during which the spent fuel rods are heated up… (more)

Subjects/Keywords: Zirconium; hydride; reorientation; dry cask storage; radial hydrides; stress; stress state; in situ; X-ray diffraction; biaxiality

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APA (6th Edition):

Cinbiz, M. N. (2015). THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27328

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):

Cinbiz, Mahmut Nedim. “THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION.” 2015. Thesis, Penn State University. Accessed March 08, 2021. https://submit-etda.libraries.psu.edu/catalog/27328.

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

MLA Handbook (7th Edition):

Cinbiz, Mahmut Nedim. “THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION.” 2015. Web. 08 Mar 2021.

Vancouver:

Cinbiz MN. THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Mar 08]. Available from: https://submit-etda.libraries.psu.edu/catalog/27328.

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

Council of Science Editors:

Cinbiz MN. THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27328

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


University of Tennessee – Knoxville

9. DeVoe, Remy Russell. Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions.

Degree: MS, Nuclear Engineering, 2015, University of Tennessee – Knoxville

Dry cask safety analyses and material degradation studies depend on reliable best- estimate thermal models. Gaps in design data and storage site conditions require… (more)

Subjects/Keywords: Thermal Modeling; Used Nuclear Fuel; Sensitivity Analysis; Nuclear Reactors; Dry Cask Storage; MAGNASTOR; Cladding Temperature; Nuclear Engineering

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APA (6th Edition):

DeVoe, R. R. (2015). Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/3469

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):

DeVoe, Remy Russell. “Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions.” 2015. Thesis, University of Tennessee – Knoxville. Accessed March 08, 2021. https://trace.tennessee.edu/utk_gradthes/3469.

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

MLA Handbook (7th Edition):

DeVoe, Remy Russell. “Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions.” 2015. Web. 08 Mar 2021.

Vancouver:

DeVoe RR. Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions. [Internet] [Thesis]. University of Tennessee – Knoxville; 2015. [cited 2021 Mar 08]. Available from: https://trace.tennessee.edu/utk_gradthes/3469.

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

Council of Science Editors:

DeVoe RR. Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions. [Thesis]. University of Tennessee – Knoxville; 2015. Available from: https://trace.tennessee.edu/utk_gradthes/3469

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


Virginia Tech

10. Wang, Meng Jen. Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking.

Degree: PhD, Nuclear Engineering, 2019, Virginia Tech

 Since the beginning of nuclear era, enormous amount of radiation applications have been proposed, developed, and applied in our daily life. The radiation is useful… (more)

Subjects/Keywords: Particle Transport Theory; Real-time; Detector Response Function Methodology; Pressure Vessel Fluence Calculations; Dosimeter/Detector Response; Dry Storage Cask External Dosimetry

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APA (6th Edition):

Wang, M. J. (2019). Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/97247

Chicago Manual of Style (16th Edition):

Wang, Meng Jen. “Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking.” 2019. Doctoral Dissertation, Virginia Tech. Accessed March 08, 2021. http://hdl.handle.net/10919/97247.

MLA Handbook (7th Edition):

Wang, Meng Jen. “Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking.” 2019. Web. 08 Mar 2021.

Vancouver:

Wang MJ. Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking. [Internet] [Doctoral dissertation]. Virginia Tech; 2019. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/10919/97247.

Council of Science Editors:

Wang MJ. Development of a Novel Detector Response Formulation and Algorithm in RAPID and its Benchmarking. [Doctoral Dissertation]. Virginia Tech; 2019. Available from: http://hdl.handle.net/10919/97247


Virginia Tech

11. Klein, Jackson Alexander. Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes.

Degree: MS, Mechanical Engineering, 2017, Virginia Tech

 Dedicated sensors are widely used throughout many industries to monitor everyday operations, maintain safety, and report performance characteristics. In order to adopt a more sustainable… (more)

Subjects/Keywords: Energy Harvesting; Nuclear Power Plant; Wireless Sensor Node; Electromagnetic Generator; Compliant Mechanism; Thermoelectric Generator; Gamma Radiation; MCNP Simulation; Gamma Heating; Dry Cask Storage

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APA (6th Edition):

Klein, J. A. (2017). Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes. (Masters Thesis). Virginia Tech. Retrieved from http://hdl.handle.net/10919/78031

Chicago Manual of Style (16th Edition):

Klein, Jackson Alexander. “Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes.” 2017. Masters Thesis, Virginia Tech. Accessed March 08, 2021. http://hdl.handle.net/10919/78031.

MLA Handbook (7th Edition):

Klein, Jackson Alexander. “Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes.” 2017. Web. 08 Mar 2021.

Vancouver:

Klein JA. Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes. [Internet] [Masters thesis]. Virginia Tech; 2017. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/10919/78031.

Council of Science Editors:

Klein JA. Energy Harvesting Opportunities Throughout the Nuclear Power Cycle for Self-Powered Wireless Sensor Nodes. [Masters Thesis]. Virginia Tech; 2017. Available from: http://hdl.handle.net/10919/78031


Brno University of Technology

12. Jestřáb, Tomáš. Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties.

Degree: 2019, Brno University of Technology

 The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally… (more)

Subjects/Keywords: vyhořelé jaderné palivo; jaderný palivový cyklus; bazén skladování; suchý mezisklad; mokrý mezisklad; obalový soubor; Dukovany; UWB1; spent nuclear fuel; nuclear fuel cycle; spent fuel pool; dry storage; wet storage; nuclear waste cask; Dukovany; UWB1

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

APA (6th Edition):

Jestřáb, T. (2019). Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/39700

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):

Jestřáb, Tomáš. “Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties.” 2019. Thesis, Brno University of Technology. Accessed March 08, 2021. http://hdl.handle.net/11012/39700.

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

MLA Handbook (7th Edition):

Jestřáb, Tomáš. “Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties.” 2019. Web. 08 Mar 2021.

Vancouver:

Jestřáb T. Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/11012/39700.

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

Council of Science Editors:

Jestřáb T. Použité jaderné palivo a jeho vlastnosti: Spent nuclear fuel and its properties. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/39700

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

13. Wierschke, Jonathan Brett. Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel.

Degree: PhD, Nuclear Engineering and Radiological Sciences, 2015, University of Michigan

 The objective of this work was to understand the long-term corrosion behavior of Boral® and Bortec® neutron absorbers during deployment in a used nuclear fuel… (more)

Subjects/Keywords: used nuclear fuel; dry cask storage; Boral; Bortec; aluminum boron carbide; Materials Science and Engineering; Nuclear Engineering and Radiological Sciences; Engineering; Science

…deployment in a used nuclear fuel dry cask storage environment for several hundred years. Corrosion… …for use in dry cask storage. The new phase formation may affect mechanical properties and… …an initiative to move more of the used fuel inventory into dry cask storage. 1.1.1 Used… …the deployment of dry cask storage of used fuel assemblies that have cooled. Even though… …the pool and cooled using natural convection in dry cask storage. Figure 3 Decay heat in… 

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

APA (6th Edition):

Wierschke, J. B. (2015). Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel. (Doctoral Dissertation). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/111438

Chicago Manual of Style (16th Edition):

Wierschke, Jonathan Brett. “Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel.” 2015. Doctoral Dissertation, University of Michigan. Accessed March 08, 2021. http://hdl.handle.net/2027.42/111438.

MLA Handbook (7th Edition):

Wierschke, Jonathan Brett. “Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel.” 2015. Web. 08 Mar 2021.

Vancouver:

Wierschke JB. Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel. [Internet] [Doctoral dissertation]. University of Michigan; 2015. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/2027.42/111438.

Council of Science Editors:

Wierschke JB. Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel. [Doctoral Dissertation]. University of Michigan; 2015. Available from: http://hdl.handle.net/2027.42/111438

14. Spencer, Kristina Yancey. Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns.

Degree: PhD, Nuclear Engineering, 2017, Texas A&M University

 To address the evolving needs of dry storage, this research developed an optimization methodology to identify loading configurations to minimize the number of casks, their… (more)

Subjects/Keywords: nuclear waste management; used nuclear fuel; dry cask storage; decay heat; multiobjective optimization; combinatorial optimization; bin packing problems; memetic algorithms; GRASP; GAMMA-PC

Storage The U.S. does not have a standardized dry cask design. Instead, a few companies offer… …HI-STORM UMAX canister storage system (CoC 1040), 10. the TN-32 dry storage cask… …x28;CoC 1021), 11. the TN-68 dry storage cask (CoC 1027), 12. the NAC-UMS… …Projected Dry Casks to Be Filled Already in Dry Cask Storage Figure 1.2: Illustration of dry… …patterns of used fuel assemblies in dry cask storage, accounting for current and future inventory… 

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

APA (6th Edition):

Spencer, K. Y. (2017). Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173097

Chicago Manual of Style (16th Edition):

Spencer, Kristina Yancey. “Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns.” 2017. Doctoral Dissertation, Texas A&M University. Accessed March 08, 2021. http://hdl.handle.net/1969.1/173097.

MLA Handbook (7th Edition):

Spencer, Kristina Yancey. “Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns.” 2017. Web. 08 Mar 2021.

Vancouver:

Spencer KY. Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns. [Internet] [Doctoral dissertation]. Texas A&M University; 2017. [cited 2021 Mar 08]. Available from: http://hdl.handle.net/1969.1/173097.

Council of Science Editors:

Spencer KY. Adaptable Long-Term Optimization of Dry Cask Storage Loading Patterns. [Doctoral Dissertation]. Texas A&M University; 2017. Available from: http://hdl.handle.net/1969.1/173097


Penn State University

15. Kern, Ludwig August. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.

Degree: 2009, Penn State University

 A FLUENT Computational Fluid Dynamics (CFD) model of a spent nuclear fuel dry storage cask was created to predict several critical design temperatures in order… (more)

Subjects/Keywords: Fluent; fluent modeling; cfd; cfd modeling; fluent model; cfd model; computational fluid dynamics; nuclear; nuclear engineering; dry storage; dry storage cask; spent fuel; spent nuclear fuel; nuclear fuel; rbmk; chernobyl; holtec; thermal; heat transfer; natural convection; convection; natural convective flow; annular; prototype; full-scale; validation; cfd code; navier-stokes; navier-stokes equation

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

APA (6th Edition):

Kern, L. A. (2009). FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/9685

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):

Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Thesis, Penn State University. Accessed March 08, 2021. https://submit-etda.libraries.psu.edu/catalog/9685.

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

MLA Handbook (7th Edition):

Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Web. 08 Mar 2021.

Vancouver:

Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Internet] [Thesis]. Penn State University; 2009. [cited 2021 Mar 08]. Available from: https://submit-etda.libraries.psu.edu/catalog/9685.

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

Council of Science Editors:

Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Thesis]. Penn State University; 2009. Available from: https://submit-etda.libraries.psu.edu/catalog/9685

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

.