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Dept: Nuclear Engineering

You searched for subject:( Light Water Reactor). Showing records 1 – 30 of 167 total matches.

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Oregon State University

1. Peguero, Lara M. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.

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

 Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of… (more)

Subjects/Keywords: Reactor physics; Light water reactors  – Uzbekistan

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APA (6th Edition):

Peguero, L. M. (2016). Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/59812

Chicago Manual of Style (16th Edition):

Peguero, Lara M. “Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.” 2016. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/59812.

MLA Handbook (7th Edition):

Peguero, Lara M. “Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor.” 2016. Web. 26 Mar 2019.

Vancouver:

Peguero LM. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/59812.

Council of Science Editors:

Peguero LM. Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/59812


Oregon State University

2. Soldatov, Alexey I. Design and analysis of a nuclear reactor core for innovative small light water reactors.

Degree: PhD, Nuclear Engineering, 2009, Oregon State University

 In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR)… (more)

Subjects/Keywords: Nuclear Reactor; Light water reactors  – Design and construction

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APA (6th Edition):

Soldatov, A. I. (2009). Design and analysis of a nuclear reactor core for innovative small light water reactors. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/11315

Chicago Manual of Style (16th Edition):

Soldatov, Alexey I. “Design and analysis of a nuclear reactor core for innovative small light water reactors.” 2009. Doctoral Dissertation, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/11315.

MLA Handbook (7th Edition):

Soldatov, Alexey I. “Design and analysis of a nuclear reactor core for innovative small light water reactors.” 2009. Web. 26 Mar 2019.

Vancouver:

Soldatov AI. Design and analysis of a nuclear reactor core for innovative small light water reactors. [Internet] [Doctoral dissertation]. Oregon State University; 2009. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/11315.

Council of Science Editors:

Soldatov AI. Design and analysis of a nuclear reactor core for innovative small light water reactors. [Doctoral Dissertation]. Oregon State University; 2009. Available from: http://hdl.handle.net/1957/11315


Penn State University

3. Magedanz, Jeffrey William. Development of High-fidelity Multi-physics System for Light Water Reactor Analysis.

Degree: PhD, Nuclear Engineering, 2013, Penn State University

 Nuclear simulation codes are vital for optimizing the performance of reactors while ensuring that they remain within regulatory safety margins. These codes tend to specialize… (more)

Subjects/Keywords: coupled codes; light water reactor simulation; high fidelity; fuel performance; discrete ordinates

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APA (6th Edition):

Magedanz, J. W. (2013). Development of High-fidelity Multi-physics System for Light Water Reactor Analysis. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/19930

Chicago Manual of Style (16th Edition):

Magedanz, Jeffrey William. “Development of High-fidelity Multi-physics System for Light Water Reactor Analysis.” 2013. Doctoral Dissertation, Penn State University. Accessed March 26, 2019. https://etda.libraries.psu.edu/catalog/19930.

MLA Handbook (7th Edition):

Magedanz, Jeffrey William. “Development of High-fidelity Multi-physics System for Light Water Reactor Analysis.” 2013. Web. 26 Mar 2019.

Vancouver:

Magedanz JW. Development of High-fidelity Multi-physics System for Light Water Reactor Analysis. [Internet] [Doctoral dissertation]. Penn State University; 2013. [cited 2019 Mar 26]. Available from: https://etda.libraries.psu.edu/catalog/19930.

Council of Science Editors:

Magedanz JW. Development of High-fidelity Multi-physics System for Light Water Reactor Analysis. [Doctoral Dissertation]. Penn State University; 2013. Available from: https://etda.libraries.psu.edu/catalog/19930


Penn State University

4. Magedanz, Jeffrey William. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.

Degree: MS, Nuclear Engineering, 2010, Penn State University

 Computer simulation of the behavior of nuclear reactors is an important part of their design, regulation, and operation. A phonomenon that is the subject of… (more)

Subjects/Keywords: boiling water reactor; stability analysis

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APA (6th Edition):

Magedanz, J. W. (2010). DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10782

Chicago Manual of Style (16th Edition):

Magedanz, Jeffrey William. “DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.” 2010. Masters Thesis, Penn State University. Accessed March 26, 2019. https://etda.libraries.psu.edu/catalog/10782.

MLA Handbook (7th Edition):

Magedanz, Jeffrey William. “DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.” 2010. Web. 26 Mar 2019.

Vancouver:

Magedanz JW. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. [Internet] [Masters thesis]. Penn State University; 2010. [cited 2019 Mar 26]. Available from: https://etda.libraries.psu.edu/catalog/10782.

Council of Science Editors:

Magedanz JW. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. [Masters Thesis]. Penn State University; 2010. Available from: https://etda.libraries.psu.edu/catalog/10782


Oregon State University

5. Bristol, Benjanmin R. Flat Plate Free Convective Heat Transfer.

Degree: MS, Nuclear Engineering, 2015, Oregon State University

 The OSU MASLWR Test facility is a scaled integral systems LOCA and proof-of-concept test facility for the Multi-Application Small Light Water Reactor design concept. A… (more)

Subjects/Keywords: free; Light water reactors

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APA (6th Edition):

Bristol, B. R. (2015). Flat Plate Free Convective Heat Transfer. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/56329

Chicago Manual of Style (16th Edition):

Bristol, Benjanmin R. “Flat Plate Free Convective Heat Transfer.” 2015. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/56329.

MLA Handbook (7th Edition):

Bristol, Benjanmin R. “Flat Plate Free Convective Heat Transfer.” 2015. Web. 26 Mar 2019.

Vancouver:

Bristol BR. Flat Plate Free Convective Heat Transfer. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/56329.

Council of Science Editors:

Bristol BR. Flat Plate Free Convective Heat Transfer. [Masters Thesis]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56329


Oregon State University

6. Hoover, Kyle J. (Kyle James). SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing.

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

 A scaling analysis of the Oregon State University (OSU) - Multi-Application Small Light Water Reactor (MASLWR) system has been developed, and an existing RELAP5-3D model… (more)

Subjects/Keywords: Scaling; Light water reactors

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APA (6th Edition):

Hoover, K. J. (. J. (2016). SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/60098

Chicago Manual of Style (16th Edition):

Hoover, Kyle J (Kyle James). “SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing.” 2016. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/60098.

MLA Handbook (7th Edition):

Hoover, Kyle J (Kyle James). “SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing.” 2016. Web. 26 Mar 2019.

Vancouver:

Hoover KJ(J. SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/60098.

Council of Science Editors:

Hoover KJ(J. SMR Full-Power Scaling Analysis and Numerical Simulation for Nuclear Hybrid Energy System Testing. [Masters Thesis]. Oregon State University; 2016. Available from: http://hdl.handle.net/1957/60098


University of Tennessee – Knoxville

7. Kapernick, Jeffrey Robert. Dynamic Modeling of a Small Modular Reactor for Control and Monitoring.

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

  A system model of the Babcock & Wilcox Generation mPower small modular reactor (SMR) was developed within the MATLAB-Simulink environment. A detailed physical configuration… (more)

Subjects/Keywords: Small modular reactor; integral pressurized water reactor; once-through steam generator; integral economizer; reactor dynamics; load following; Nuclear Engineering

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APA (6th Edition):

Kapernick, J. R. (2015). Dynamic Modeling of a Small Modular Reactor for Control and Monitoring. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/3377

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):

Kapernick, Jeffrey Robert. “Dynamic Modeling of a Small Modular Reactor for Control and Monitoring.” 2015. Thesis, University of Tennessee – Knoxville. Accessed March 26, 2019. https://trace.tennessee.edu/utk_gradthes/3377.

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

MLA Handbook (7th Edition):

Kapernick, Jeffrey Robert. “Dynamic Modeling of a Small Modular Reactor for Control and Monitoring.” 2015. Web. 26 Mar 2019.

Vancouver:

Kapernick JR. Dynamic Modeling of a Small Modular Reactor for Control and Monitoring. [Internet] [Thesis]. University of Tennessee – Knoxville; 2015. [cited 2019 Mar 26]. Available from: https://trace.tennessee.edu/utk_gradthes/3377.

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

Council of Science Editors:

Kapernick JR. Dynamic Modeling of a Small Modular Reactor for Control and Monitoring. [Thesis]. University of Tennessee – Knoxville; 2015. Available from: https://trace.tennessee.edu/utk_gradthes/3377

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


Oregon State University

8. Brigantic, Adam. Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor.

Degree: MS, Nuclear Engineering, 2014, Oregon State University

 Small modular reactors (SMRs) are a recent advancement in commercial nuclear reactor design with growing interest worldwide. New SMR concepts, such as the Multi-Application Small… (more)

Subjects/Keywords: uncertainty; Light water reactors  – Mathematical models

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APA (6th Edition):

Brigantic, A. (2014). Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/53095

Chicago Manual of Style (16th Edition):

Brigantic, Adam. “Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor.” 2014. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/53095.

MLA Handbook (7th Edition):

Brigantic, Adam. “Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor.” 2014. Web. 26 Mar 2019.

Vancouver:

Brigantic A. Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor. [Internet] [Masters thesis]. Oregon State University; 2014. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/53095.

Council of Science Editors:

Brigantic A. Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor. [Masters Thesis]. Oregon State University; 2014. Available from: http://hdl.handle.net/1957/53095


Oregon State University

9. Haugh, Brandon Patrick. Multi application small light water reactor containment analysis and design.

Degree: MS, Nuclear Engineering, 2002, Oregon State University

 This thesis presents the assessment of the Multi Application Small Light Water Reactor (MASLWR) containment design during steady-state and transient conditions. The MASLWR project is… (more)

Subjects/Keywords: Light water reactors

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APA (6th Edition):

Haugh, B. P. (2002). Multi application small light water reactor containment analysis and design. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/31661

Chicago Manual of Style (16th Edition):

Haugh, Brandon Patrick. “Multi application small light water reactor containment analysis and design.” 2002. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/31661.

MLA Handbook (7th Edition):

Haugh, Brandon Patrick. “Multi application small light water reactor containment analysis and design.” 2002. Web. 26 Mar 2019.

Vancouver:

Haugh BP. Multi application small light water reactor containment analysis and design. [Internet] [Masters thesis]. Oregon State University; 2002. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/31661.

Council of Science Editors:

Haugh BP. Multi application small light water reactor containment analysis and design. [Masters Thesis]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/31661


Oregon State University

10. Galvin, Mark Robert, 1967-. System model of a natural circulation integral test facility.

Degree: PhD, Nuclear Engineering, 2009, Oregon State University

 The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since… (more)

Subjects/Keywords: Light water reactors  – Design and construction  – Mathematical models

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APA (6th Edition):

Galvin, Mark Robert, 1. (2009). System model of a natural circulation integral test facility. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/11914

Chicago Manual of Style (16th Edition):

Galvin, Mark Robert, 1967-. “System model of a natural circulation integral test facility.” 2009. Doctoral Dissertation, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/11914.

MLA Handbook (7th Edition):

Galvin, Mark Robert, 1967-. “System model of a natural circulation integral test facility.” 2009. Web. 26 Mar 2019.

Vancouver:

Galvin, Mark Robert 1. System model of a natural circulation integral test facility. [Internet] [Doctoral dissertation]. Oregon State University; 2009. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/11914.

Council of Science Editors:

Galvin, Mark Robert 1. System model of a natural circulation integral test facility. [Doctoral Dissertation]. Oregon State University; 2009. Available from: http://hdl.handle.net/1957/11914

11. Mullin, Etienne M. High Pressure Condensation in an SMR Containment.

Degree: MS, Nuclear Engineering, 2015, Oregon State University

 The Oregon State University Multi-Application Small Light Water Reactor test facility is employed in a series tests to evaluate condensation heat transfer in small, high… (more)

Subjects/Keywords: Light water reactors

…Modular Reactor Oregon State University Multi-Application Small Light Water Reactor Emergency… …Application Small Light Water Reactor (MASLWR) concept, the precursor to the NuScale Power… …Reactor Pressurized Water Reactor High Pressure Containment Heat Transfer Plate Cooling Pool… …is a small pressurized water reactor that relies on natural circulation to provide core… …Core Cooling System Loss of Coolant Accident Passive Containment Cooling System Boiling Water… 

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APA (6th Edition):

Mullin, E. M. (2015). High Pressure Condensation in an SMR Containment. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/56284

Chicago Manual of Style (16th Edition):

Mullin, Etienne M. “High Pressure Condensation in an SMR Containment.” 2015. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/56284.

MLA Handbook (7th Edition):

Mullin, Etienne M. “High Pressure Condensation in an SMR Containment.” 2015. Web. 26 Mar 2019.

Vancouver:

Mullin EM. High Pressure Condensation in an SMR Containment. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/56284.

Council of Science Editors:

Mullin EM. High Pressure Condensation in an SMR Containment. [Masters Thesis]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56284


University of South Carolina

12. Carroll, Spencer. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.

Degree: MS, Nuclear Engineering, 2014, University of South Carolina

  As current reactors approach the end of their operable lifetime, new reactors are needed if nuclear power is to continue being generated in the… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Implementation; Evaluation; Fuel Creep; Light-Water; FRAPCON

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APA (6th Edition):

Carroll, S. (2014). Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/3581

Chicago Manual of Style (16th Edition):

Carroll, Spencer. “Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.” 2014. Masters Thesis, University of South Carolina. Accessed March 26, 2019. https://scholarcommons.sc.edu/etd/3581.

MLA Handbook (7th Edition):

Carroll, Spencer. “Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5.” 2014. Web. 26 Mar 2019.

Vancouver:

Carroll S. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. [Internet] [Masters thesis]. University of South Carolina; 2014. [cited 2019 Mar 26]. Available from: https://scholarcommons.sc.edu/etd/3581.

Council of Science Editors:

Carroll S. Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5. [Masters Thesis]. University of South Carolina; 2014. Available from: https://scholarcommons.sc.edu/etd/3581


Texas A&M University

13. Solom, Matthew Alan. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.

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

 In current Station Blackout analyses for Generation II Light Water Reactors, battery failure in 4-8 hours is expected to result in the failure of the… (more)

Subjects/Keywords: thermal stratification; chugging; Direct Contact Condensation (DCC); Reactor Core Isolation Cooling (RCIC) System; Boiling Water Reactor (BWR); suppression pool; Station Blackout (SBO)

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APA (6th Edition):

Solom, M. A. (2016). Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/157135

Chicago Manual of Style (16th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Doctoral Dissertation, Texas A&M University. Accessed March 26, 2019. http://hdl.handle.net/1969.1/157135.

MLA Handbook (7th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Web. 26 Mar 2019.

Vancouver:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1969.1/157135.

Council of Science Editors:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/157135


Penn State University

14. Younker, Ian Mark. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.

Degree: MS, Nuclear Engineering, 2015, Penn State University

 Accident tolerant fuels (ATF) are designed to mitigate the detrimental interaction between zirconium-alloy cladding and high temperature steam found during beyond design basis accident conditions.… (more)

Subjects/Keywords: Light water reactors; Accident Tolerant Fuel; Ceramic coatings for clad; Alternative clad

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APA (6th Edition):

Younker, I. M. (2015). Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/25009

Chicago Manual of Style (16th Edition):

Younker, Ian Mark. “Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.” 2015. Masters Thesis, Penn State University. Accessed March 26, 2019. https://etda.libraries.psu.edu/catalog/25009.

MLA Handbook (7th Edition):

Younker, Ian Mark. “Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors.” 2015. Web. 26 Mar 2019.

Vancouver:

Younker IM. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. [Internet] [Masters thesis]. Penn State University; 2015. [cited 2019 Mar 26]. Available from: https://etda.libraries.psu.edu/catalog/25009.

Council of Science Editors:

Younker IM. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors. [Masters Thesis]. Penn State University; 2015. Available from: https://etda.libraries.psu.edu/catalog/25009

15. Mai, Anh T. Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3.

Degree: MS, Nuclear Engineering, 2011, Oregon State University

 The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU)… (more)

Subjects/Keywords: MASLWR; Light water reactors  – Evaluation

Light Water Reactor (LWR) designs currently in development. ............ 9 Table 2.2… …and Environmental Laboratory Light Water Reactor Multi-Application Small Light Water Reactor… …Fuel Performance Analysis for Innovative Small Light Water Reactor Using VIPRE-01 and FRAPCON… …the navy. Generally, small light water reactor concepts are expected to have simpler… …University proposed the Multi-Application Small Light Water Reactor (MASLWR) design in… 

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APA (6th Edition):

Mai, A. T. (2011). Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/26964

Chicago Manual of Style (16th Edition):

Mai, Anh T. “Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3.” 2011. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/26964.

MLA Handbook (7th Edition):

Mai, Anh T. “Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3.” 2011. Web. 26 Mar 2019.

Vancouver:

Mai AT. Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3. [Internet] [Masters thesis]. Oregon State University; 2011. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/26964.

Council of Science Editors:

Mai AT. Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3. [Masters Thesis]. Oregon State University; 2011. Available from: http://hdl.handle.net/1957/26964


University of South Carolina

16. Metzger, Kathryn E. Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors.

Degree: PhD, Nuclear Engineering, 2016, University of South Carolina

  Following the accident at the Fukushima plant, enhancing the accident tolerance of the light water reactor (LWR) fleet became a topic of serious discussion.… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Analysis; Pellet Cladding Interaction; Creep Of U3Si2 Fuel; Light Water Reactors

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APA (6th Edition):

Metzger, K. E. (2016). Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors. (Doctoral Dissertation). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/3811

Chicago Manual of Style (16th Edition):

Metzger, Kathryn E. “Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors.” 2016. Doctoral Dissertation, University of South Carolina. Accessed March 26, 2019. https://scholarcommons.sc.edu/etd/3811.

MLA Handbook (7th Edition):

Metzger, Kathryn E. “Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors.” 2016. Web. 26 Mar 2019.

Vancouver:

Metzger KE. Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors. [Internet] [Doctoral dissertation]. University of South Carolina; 2016. [cited 2019 Mar 26]. Available from: https://scholarcommons.sc.edu/etd/3811.

Council of Science Editors:

Metzger KE. Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors. [Doctoral Dissertation]. University of South Carolina; 2016. Available from: https://scholarcommons.sc.edu/etd/3811


Penn State University

17. Kim, Han Sang. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.

Degree: PhD, Nuclear Engineering, 2007, Penn State University

 Existing computer codes, developed by Macdonald et al. for modeling water chemistry and estimating the accumulated damage from the stress corrosion cracking in the operating… (more)

Subjects/Keywords: Impedance measurement; Polarization curve; Corrosion potential; Boiling water reactor; Pressurized water reactor; Point defect model

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APA (6th Edition):

Kim, H. S. (2007). A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/8076

Chicago Manual of Style (16th Edition):

Kim, Han Sang. “A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.” 2007. Doctoral Dissertation, Penn State University. Accessed March 26, 2019. https://etda.libraries.psu.edu/catalog/8076.

MLA Handbook (7th Edition):

Kim, Han Sang. “A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.” 2007. Web. 26 Mar 2019.

Vancouver:

Kim HS. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. [Internet] [Doctoral dissertation]. Penn State University; 2007. [cited 2019 Mar 26]. Available from: https://etda.libraries.psu.edu/catalog/8076.

Council of Science Editors:

Kim HS. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. [Doctoral Dissertation]. Penn State University; 2007. Available from: https://etda.libraries.psu.edu/catalog/8076

18. Bowser, Christopher Jordan. RELAP5-3D modeling of ADS blowdown of MASLWR facility.

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

 Oregon State University has hosted an International Atomic Energy Agency (IAEA) International Collaborative Standard Problem (ICSP) through testing conducted on the Multi-Application Small Light Water(more)

Subjects/Keywords: Nuclear; Light water reactors  – Safety measures

Light Water Reactor (MASLWR) facility at Oregon State University (OSU)… …Westinghouse’s AP1000 and General Electric-Hitachi’s Economic Simple Boiling Water Reactor when the… …light water SMR. The MASLWR facility is an integral test facility of a full-time natural… …water reactor designs, there are a number of non-technical issues that have been identified by… …that differ from the typical western pressurized water reactor (PWR) design. A… 

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APA (6th Edition):

Bowser, C. J. (2012). RELAP5-3D modeling of ADS blowdown of MASLWR facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/30438

Chicago Manual of Style (16th Edition):

Bowser, Christopher Jordan. “RELAP5-3D modeling of ADS blowdown of MASLWR facility.” 2012. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/30438.

MLA Handbook (7th Edition):

Bowser, Christopher Jordan. “RELAP5-3D modeling of ADS blowdown of MASLWR facility.” 2012. Web. 26 Mar 2019.

Vancouver:

Bowser CJ. RELAP5-3D modeling of ADS blowdown of MASLWR facility. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/30438.

Council of Science Editors:

Bowser CJ. RELAP5-3D modeling of ADS blowdown of MASLWR facility. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/30438

19. Casey, Jason R. High pressure condensation heat transfer in the evacuated containment of a small modular reactor.

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

 At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support… (more)

Subjects/Keywords: Condensation; Light water reactors  – Safety measures

…LOCA ADS PLC DACS ATHRL Multi‐Application Small Light Water Reactor High… …scale. The Multi‐Application Small Light Water Reactor (MASLWR) research… …MASLWR reactor concept illustration… …13 15 3.1‐1: Reactor pressure vessel cross‐sectional view… …Pressure Containment Reactor Pressure Vessel Cooling Pool Vessel Heat Transfer Plate NuScale… 

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APA (6th Edition):

Casey, J. R. (2012). High pressure condensation heat transfer in the evacuated containment of a small modular reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/36283

Chicago Manual of Style (16th Edition):

Casey, Jason R. “High pressure condensation heat transfer in the evacuated containment of a small modular reactor.” 2012. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/36283.

MLA Handbook (7th Edition):

Casey, Jason R. “High pressure condensation heat transfer in the evacuated containment of a small modular reactor.” 2012. Web. 26 Mar 2019.

Vancouver:

Casey JR. High pressure condensation heat transfer in the evacuated containment of a small modular reactor. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/36283.

Council of Science Editors:

Casey JR. High pressure condensation heat transfer in the evacuated containment of a small modular reactor. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/36283


MIT

20. Loh, Wee Tee. The use of burnable poison to improve uranium utilization in PWRS .

Degree: PhD, Nuclear Engineering, 1982, MIT

Subjects/Keywords: Nuclear Engineering.; Pressurized water reactors; Light water reactors; Uranium; Nuclear fuel elements

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APA (6th Edition):

Loh, W. T. (1982). The use of burnable poison to improve uranium utilization in PWRS . (Doctoral Dissertation). MIT. Retrieved from http://hdl.handle.net/1721.1/15766

Chicago Manual of Style (16th Edition):

Loh, Wee Tee. “The use of burnable poison to improve uranium utilization in PWRS .” 1982. Doctoral Dissertation, MIT. Accessed March 26, 2019. http://hdl.handle.net/1721.1/15766.

MLA Handbook (7th Edition):

Loh, Wee Tee. “The use of burnable poison to improve uranium utilization in PWRS .” 1982. Web. 26 Mar 2019.

Vancouver:

Loh WT. The use of burnable poison to improve uranium utilization in PWRS . [Internet] [Doctoral dissertation]. MIT; 1982. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1721.1/15766.

Council of Science Editors:

Loh WT. The use of burnable poison to improve uranium utilization in PWRS . [Doctoral Dissertation]. MIT; 1982. Available from: http://hdl.handle.net/1721.1/15766


MIT

21. Parsons, Donald Kent. Application of response matrix methods to PWR analysis .

Degree: MS, Nuclear Engineering, 1982, MIT

Subjects/Keywords: Nuclear Engineering.; Pressurized water reactors; Neutron flux Mathematical models; Light water reactors

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APA (6th Edition):

Parsons, D. K. (1982). Application of response matrix methods to PWR analysis . (Masters Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/17166

Chicago Manual of Style (16th Edition):

Parsons, Donald Kent. “Application of response matrix methods to PWR analysis .” 1982. Masters Thesis, MIT. Accessed March 26, 2019. http://hdl.handle.net/1721.1/17166.

MLA Handbook (7th Edition):

Parsons, Donald Kent. “Application of response matrix methods to PWR analysis .” 1982. Web. 26 Mar 2019.

Vancouver:

Parsons DK. Application of response matrix methods to PWR analysis . [Internet] [Masters thesis]. MIT; 1982. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1721.1/17166.

Council of Science Editors:

Parsons DK. Application of response matrix methods to PWR analysis . [Masters Thesis]. MIT; 1982. Available from: http://hdl.handle.net/1721.1/17166


MIT

22. Loomis, James North. Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT .

Degree: Nuclear Engineering, 1981, MIT

Subjects/Keywords: Nuclear Engineering.; Nuclear fuel elements Computer programs; Boiling water reactors Fluid dynamics; Boiling water reactors Thermal properties; Pressurized water reactors Fluid dynamics; Pressurized water reactors Thermal properties; Light water reactors Fluid dynamics; Light water reactors Thermal properties

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APA (6th Edition):

Loomis, J. N. (1981). Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT . (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/15764

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):

Loomis, James North. “Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT .” 1981. Thesis, MIT. Accessed March 26, 2019. http://hdl.handle.net/1721.1/15764.

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

MLA Handbook (7th Edition):

Loomis, James North. “Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT .” 1981. Web. 26 Mar 2019.

Vancouver:

Loomis JN. Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT . [Internet] [Thesis]. MIT; 1981. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1721.1/15764.

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

Council of Science Editors:

Loomis JN. Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT . [Thesis]. MIT; 1981. Available from: http://hdl.handle.net/1721.1/15764

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

23. Hallee, Brian Todd. Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method.

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

 The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been… (more)

Subjects/Keywords: APEX; Light water reactors  – Safety measures  – Mathematical models

…Westinghouse AP1000 reactor as part of the light water reactor sustainability program. In lieu of the… …shape the outcome. Resulting safety margins obtained as part of the light-water reactor… …light-water sustainability program for the validation of next-generation system safety… …functions of a primary feed-and-bleed IET in support of the light-water sustainability program and… …acceptance criteria for light-water reactors (10.CFR.50.46) to allow the use of best… 

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APA (6th Edition):

Hallee, B. T. (2013). Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/37872

Chicago Manual of Style (16th Edition):

Hallee, Brian Todd. “Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method.” 2013. Masters Thesis, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/37872.

MLA Handbook (7th Edition):

Hallee, Brian Todd. “Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method.” 2013. Web. 26 Mar 2019.

Vancouver:

Hallee BT. Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method. [Internet] [Masters thesis]. Oregon State University; 2013. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/37872.

Council of Science Editors:

Hallee BT. Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method. [Masters Thesis]. Oregon State University; 2013. Available from: http://hdl.handle.net/1957/37872


MIT

24. Smith, Kord Sterling. Spatial homogenization methods for light water reactor analysis .

Degree: PhD, Nuclear Engineering, 1980, MIT

Subjects/Keywords: Nuclear Engineering.; Light water reactors; Neutron transport theory; Nuclear reactors Tables

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APA (6th Edition):

Smith, K. S. (1980). Spatial homogenization methods for light water reactor analysis . (Doctoral Dissertation). MIT. Retrieved from http://hdl.handle.net/1721.1/16042

Chicago Manual of Style (16th Edition):

Smith, Kord Sterling. “Spatial homogenization methods for light water reactor analysis .” 1980. Doctoral Dissertation, MIT. Accessed March 26, 2019. http://hdl.handle.net/1721.1/16042.

MLA Handbook (7th Edition):

Smith, Kord Sterling. “Spatial homogenization methods for light water reactor analysis .” 1980. Web. 26 Mar 2019.

Vancouver:

Smith KS. Spatial homogenization methods for light water reactor analysis . [Internet] [Doctoral dissertation]. MIT; 1980. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1721.1/16042.

Council of Science Editors:

Smith KS. Spatial homogenization methods for light water reactor analysis . [Doctoral Dissertation]. MIT; 1980. Available from: http://hdl.handle.net/1721.1/16042


MIT

25. Rivera, John Edward. Performance of light water reactor fuel rods during plant power changes .

Degree: Nuclear Engineering, 1981, MIT

Subjects/Keywords: Nuclear Engineering.; Light water reactors; Nuclear fuel rods; Nuclear fuel claddings; Zircaloy-2

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APA (6th Edition):

Rivera, J. E. (1981). Performance of light water reactor fuel rods during plant power changes . (Thesis). MIT. Retrieved from http://hdl.handle.net/1721.1/15854

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):

Rivera, John Edward. “Performance of light water reactor fuel rods during plant power changes .” 1981. Thesis, MIT. Accessed March 26, 2019. http://hdl.handle.net/1721.1/15854.

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

MLA Handbook (7th Edition):

Rivera, John Edward. “Performance of light water reactor fuel rods during plant power changes .” 1981. Web. 26 Mar 2019.

Vancouver:

Rivera JE. Performance of light water reactor fuel rods during plant power changes . [Internet] [Thesis]. MIT; 1981. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1721.1/15854.

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

Council of Science Editors:

Rivera JE. Performance of light water reactor fuel rods during plant power changes . [Thesis]. MIT; 1981. Available from: http://hdl.handle.net/1721.1/15854

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


Oregon State University

26. Gullekson, Brian J. Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems.

Degree: PhD, Nuclear Engineering, 2017, Oregon State University

 Partitioning of trivalent actinides (in particular, americium and curium) from the fission produced light lanthanides is a major concern of used nuclear fuel reprocessing for… (more)

Subjects/Keywords: TALSPEAK; Reactor fuel reprocessing

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APA (6th Edition):

Gullekson, B. J. (2017). Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/60150

Chicago Manual of Style (16th Edition):

Gullekson, Brian J. “Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems.” 2017. Doctoral Dissertation, Oregon State University. Accessed March 26, 2019. http://hdl.handle.net/1957/60150.

MLA Handbook (7th Edition):

Gullekson, Brian J. “Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems.” 2017. Web. 26 Mar 2019.

Vancouver:

Gullekson BJ. Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems. [Internet] [Doctoral dissertation]. Oregon State University; 2017. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1957/60150.

Council of Science Editors:

Gullekson BJ. Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems. [Doctoral Dissertation]. Oregon State University; 2017. Available from: http://hdl.handle.net/1957/60150


Texas A&M University

27. Kumar, Akansha. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.

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

 The optimization of a complex system involves the determination of optimum values for a set of design parameters. The optimization search happens in order to… (more)

Subjects/Keywords: genetic algorithms; optimization; nuclear; reactor

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APA (6th Edition):

Kumar, A. (2016). An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/159121

Chicago Manual of Style (16th Edition):

Kumar, Akansha. “An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.” 2016. Doctoral Dissertation, Texas A&M University. Accessed March 26, 2019. http://hdl.handle.net/1969.1/159121.

MLA Handbook (7th Edition):

Kumar, Akansha. “An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications.” 2016. Web. 26 Mar 2019.

Vancouver:

Kumar A. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2019 Mar 26]. Available from: http://hdl.handle.net/1969.1/159121.

Council of Science Editors:

Kumar A. An Iterative Optimization Method Using Genetic Algorithms and Gaussian Process Based Regression in Nuclear Reactor Design Applications. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/159121


Missouri University of Science and Technology

28. Tucker, Lucas Powelson. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP.

Degree: PhD, Nuclear Engineering, Missouri University of Science and Technology

  "This dissertation investigates techniques for spent fuel monitoring, and assesses the feasibility of using a thorium-based mixed oxide fuel in a conventional pressurized water(more)

Subjects/Keywords: MCNP; Monte Carlo N-Particle code; Mixed oxide fuel; Pressurized water reactor; Nuclear Engineering

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APA (6th Edition):

Tucker, L. P. (n.d.). Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP. (Doctoral Dissertation). Missouri University of Science and Technology. Retrieved from http://scholarsmine.mst.edu/doctoral_dissertations/2492

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Chicago Manual of Style (16th Edition):

Tucker, Lucas Powelson. “Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP.” Doctoral Dissertation, Missouri University of Science and Technology. Accessed March 26, 2019. http://scholarsmine.mst.edu/doctoral_dissertations/2492.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

MLA Handbook (7th Edition):

Tucker, Lucas Powelson. “Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP.” Web. 26 Mar 2019.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Vancouver:

Tucker LP. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP. [Internet] [Doctoral dissertation]. Missouri University of Science and Technology; [cited 2019 Mar 26]. Available from: http://scholarsmine.mst.edu/doctoral_dissertations/2492.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Council of Science Editors:

Tucker LP. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP. [Doctoral Dissertation]. Missouri University of Science and Technology; Available from: http://scholarsmine.mst.edu/doctoral_dissertations/2492

Note: this citation may be lacking information needed for this citation format:
No year of publication.

29. Hays, Ross D. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.

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

 A commercial nuclear power plant with a boiling water reactor will utilize between 368 and 800+ individual fuel assemblies to generate steam for 18 to… (more)

Subjects/Keywords: Boiling Water Reactor; BWR;

…52 1 Chapter 1 Introduction The operation of a commercial Light Water Reactor (LWR… …limitations. As the typical Boiling Water Reactor core contains between 368 and 800 fuel assemblies… …consideration unique to BWRs is the sequencing of the control rods. Unlike a Pressurized Water Reactor… …x29; power reactor involves the controlled conversion of energy stored in the nucleus of a… …its useful life span it is removed from the reactor and replaced with a fresh assembly. For… 

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APA (6th Edition):

Hays, R. D. (2009). Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. (Thesis). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/2746

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):

Hays, Ross D. “Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.” 2009. Thesis, North Carolina State University. Accessed March 26, 2019. http://www.lib.ncsu.edu/resolver/1840.16/2746.

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

MLA Handbook (7th Edition):

Hays, Ross D. “Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.” 2009. Web. 26 Mar 2019.

Vancouver:

Hays RD. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. [Internet] [Thesis]. North Carolina State University; 2009. [cited 2019 Mar 26]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/2746.

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

Council of Science Editors:

Hays RD. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. [Thesis]. North Carolina State University; 2009. Available from: http://www.lib.ncsu.edu/resolver/1840.16/2746

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


The Ohio State University

30. Kennedy, Ryanne Ariel. Quantifying Uncertainty in Reactor Flux/Power Distributions.

Degree: PhD, Nuclear Engineering, 2011, The Ohio State University

 The design and development of a conceptual system for power measurements in a reactor core using in-core sensors has been an ongoing focus of research… (more)

Subjects/Keywords: Nuclear Engineering; nuclear reactor; flux; uncertainty quantification; reactor physics

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APA (6th Edition):

Kennedy, R. A. (2011). Quantifying Uncertainty in Reactor Flux/Power Distributions. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901

Chicago Manual of Style (16th Edition):

Kennedy, Ryanne Ariel. “Quantifying Uncertainty in Reactor Flux/Power Distributions.” 2011. Doctoral Dissertation, The Ohio State University. Accessed March 26, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901.

MLA Handbook (7th Edition):

Kennedy, Ryanne Ariel. “Quantifying Uncertainty in Reactor Flux/Power Distributions.” 2011. Web. 26 Mar 2019.

Vancouver:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Internet] [Doctoral dissertation]. The Ohio State University; 2011. [cited 2019 Mar 26]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901.

Council of Science Editors:

Kennedy RA. Quantifying Uncertainty in Reactor Flux/Power Distributions. [Doctoral Dissertation]. The Ohio State University; 2011. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306360901

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