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You searched for +publisher:"Oregon State University" +contributor:("Wu, Qiao"). Showing records 1 – 25 of 25 total matches.

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Oregon State University

1. Nelson, Roy K. Pressure losses across a 180 degree turn in the AP1000 cooling annulus.

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

 A one-sixth scaled facility was constructed at Oregon State University to determine the pressure losses around Westinghouse's AP1000 Passive Containment Cooling System. An explanation of… (more)

Subjects/Keywords: AP1000; Pressurized water reactors  – Cooling

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APA (6th Edition):

Nelson, R. K. (2008). Pressure losses across a 180 degree turn in the AP1000 cooling annulus. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/9974

Chicago Manual of Style (16th Edition):

Nelson, Roy K. “Pressure losses across a 180 degree turn in the AP1000 cooling annulus.” 2008. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/9974.

MLA Handbook (7th Edition):

Nelson, Roy K. “Pressure losses across a 180 degree turn in the AP1000 cooling annulus.” 2008. Web. 20 Mar 2019.

Vancouver:

Nelson RK. Pressure losses across a 180 degree turn in the AP1000 cooling annulus. [Internet] [Masters thesis]. Oregon State University; 2008. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/9974.

Council of Science Editors:

Nelson RK. Pressure losses across a 180 degree turn in the AP1000 cooling annulus. [Masters Thesis]. Oregon State University; 2008. Available from: http://hdl.handle.net/1957/9974


Oregon State University

2. 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 20, 2019. http://hdl.handle.net/1957/56329.

MLA Handbook (7th Edition):

Bristol, Benjanmin R. “Flat Plate Free Convective Heat Transfer.” 2015. Web. 20 Mar 2019.

Vancouver:

Bristol BR. Flat Plate Free Convective Heat Transfer. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Mar 20]. 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

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

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

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

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

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Luo, Hu. “Quantified PIRT and uncertainty quantification for computer code validation.” 2012. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/35475.

MLA Handbook (7th Edition):

Luo, Hu. “Quantified PIRT and uncertainty quantification for computer code validation.” 2012. Web. 20 Mar 2019.

Vancouver:

Luo H. Quantified PIRT and uncertainty quantification for computer code validation. [Internet] [Doctoral dissertation]. Oregon State University; 2012. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/35475.

Council of Science Editors:

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


Oregon State University

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

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

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

Subjects/Keywords: iGrav; Nuclear reactors  – Cooling

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APA (6th Edition):

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

Chicago Manual of Style (16th Edition):

Danielson, Jordan J. “Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring.” 2016. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/60093.

MLA Handbook (7th Edition):

Danielson, Jordan J. “Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring.” 2016. Web. 20 Mar 2019.

Vancouver:

Danielson JJ. Gravity-Based Non-Invasive Superconducting Gravimeter System for Reactor Coolant Inventory Monitoring. [Internet] [Masters thesis]. Oregon State University; 2016. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/60093.

Council of Science Editors:

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


Oregon State University

5. 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 20, 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. 20 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 20]. 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

6. Luitjens, Jeffrey M. The Development of a Mechanistic Critical Heat Flux Correlation.

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

 A mechanistic based critical heat flux (CHF) correlation has been developed derived from a mass, momentum, and energy balance at a nucleation site for water.… (more)

Subjects/Keywords: CHF; Pressurized water reactors  – Critical heat flux  – Mathematical modeling

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APA (6th Edition):

Luitjens, J. M. (2015). The Development of a Mechanistic Critical Heat Flux Correlation. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/56128

Chicago Manual of Style (16th Edition):

Luitjens, Jeffrey M. “The Development of a Mechanistic Critical Heat Flux Correlation.” 2015. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/56128.

MLA Handbook (7th Edition):

Luitjens, Jeffrey M. “The Development of a Mechanistic Critical Heat Flux Correlation.” 2015. Web. 20 Mar 2019.

Vancouver:

Luitjens JM. The Development of a Mechanistic Critical Heat Flux Correlation. [Internet] [Doctoral dissertation]. Oregon State University; 2015. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/56128.

Council of Science Editors:

Luitjens JM. The Development of a Mechanistic Critical Heat Flux Correlation. [Doctoral Dissertation]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56128

7. Wuth, Bradyn J. Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator.

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

 Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural… (more)

Subjects/Keywords: helical coil; Heat exchangers

…Nexant-Bechtel, Inc., and Oregon State University (OSU) known as the Multi… …Oregon State University. \ith data from the facility, a heat transfer coefcient (HTC… 

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APA (6th Edition):

Wuth, B. J. (2014). Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/50657

Chicago Manual of Style (16th Edition):

Wuth, Bradyn J. “Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator.” 2014. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/50657.

MLA Handbook (7th Edition):

Wuth, Bradyn J. “Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator.” 2014. Web. 20 Mar 2019.

Vancouver:

Wuth BJ. Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator. [Internet] [Masters thesis]. Oregon State University; 2014. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/50657.

Council of Science Editors:

Wuth BJ. Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator. [Masters Thesis]. Oregon State University; 2014. Available from: http://hdl.handle.net/1957/50657

8. 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

…99 2.3 Chapter 1: Introduction Oregon State University has recently updated the Advanced… 

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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 20, 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. 20 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 20]. 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

9. Gradecka, Malwina. Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor.

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

 Since High Temperature Gas-cooled Reactors are being considered as most promising design of upcoming IV Gen reactors, thus key research areas were identified to address… (more)

Subjects/Keywords: HTR; Gas cooled reactors

…with coolant jet mixing. The HTTF located at Oregon State University was used as a reference… 

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APA (6th Edition):

Gradecka, M. (2015). Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/56282

Chicago Manual of Style (16th Edition):

Gradecka, Malwina. “Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor.” 2015. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/56282.

MLA Handbook (7th Edition):

Gradecka, Malwina. “Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor.” 2015. Web. 20 Mar 2019.

Vancouver:

Gradecka M. Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor. [Internet] [Doctoral dissertation]. Oregon State University; 2015. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/56282.

Council of Science Editors:

Gradecka M. Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor. [Doctoral Dissertation]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56282

10. 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… …Nexant-Bechtel, and Oregon State University with support from the Department of Energy (… …on the Oregon State University (OSU) campus, is scaled to 1:3 height and features… 

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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 20, 2019. http://hdl.handle.net/1957/56284.

MLA Handbook (7th Edition):

Mullin, Etienne M. “High Pressure Condensation in an SMR Containment.” 2015. Web. 20 Mar 2019.

Vancouver:

Mullin EM. High Pressure Condensation in an SMR Containment. [Internet] [Masters thesis]. Oregon State University; 2015. [cited 2019 Mar 20]. 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

11. Cadell, Seth R. Development of a binary mixture gas composition instrument for use in a confined high temperature environment.

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

 With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a… (more)

Subjects/Keywords: HTGR; Gas cooled reactors  – Equipment and supplies  – Effect of high temperatures on

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APA (6th Edition):

Cadell, S. R. (2012). Development of a binary mixture gas composition instrument for use in a confined high temperature environment. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/36206

Chicago Manual of Style (16th Edition):

Cadell, Seth R. “Development of a binary mixture gas composition instrument for use in a confined high temperature environment.” 2012. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/36206.

MLA Handbook (7th Edition):

Cadell, Seth R. “Development of a binary mixture gas composition instrument for use in a confined high temperature environment.” 2012. Web. 20 Mar 2019.

Vancouver:

Cadell SR. Development of a binary mixture gas composition instrument for use in a confined high temperature environment. [Internet] [Doctoral dissertation]. Oregon State University; 2012. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/36206.

Council of Science Editors:

Cadell SR. Development of a binary mixture gas composition instrument for use in a confined high temperature environment. [Doctoral Dissertation]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/36206

12. Utberg, John E., Jr. Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility.

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

 The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the… (more)

Subjects/Keywords: MHTGR; Gas cooled reactors  – Oregon  – Corvallis  – Testing

…guillotine break (DEGB). 1.2 High-Temperature Test Facility At Oregon State University… …State University PCC Pressurized Conduction Cooldown P-LOFC Pressurized Loss of Forced… …Modular High Temperature Gas-Cooled Reactor NGNP Next Generation Nuclear Plant OSU Oregon… 

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APA (6th Edition):

Utberg, John E., J. (2013). Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/43338

Chicago Manual of Style (16th Edition):

Utberg, John E., Jr. “Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility.” 2013. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/43338.

MLA Handbook (7th Edition):

Utberg, John E., Jr. “Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility.” 2013. Web. 20 Mar 2019.

Vancouver:

Utberg, John E. J. Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility. [Internet] [Masters thesis]. Oregon State University; 2013. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/43338.

Council of Science Editors:

Utberg, John E. J. Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility. [Masters Thesis]. Oregon State University; 2013. Available from: http://hdl.handle.net/1957/43338

13. Nelson, Benjamin L. Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility.

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

 The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility… (more)

Subjects/Keywords: VHTR; Pebble bed reactors  – Mathematical models

…cooperative agreement between the NRC, Oregon State University (OSU), Texas A&M University… …2.2 VHTR Scaling Analyses In 2005 Oregon State University professors conducted a scaling… 

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APA (6th Edition):

Nelson, B. L. (2009). Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/11999

Chicago Manual of Style (16th Edition):

Nelson, Benjamin L. “Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility.” 2009. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/11999.

MLA Handbook (7th Edition):

Nelson, Benjamin L. “Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility.” 2009. Web. 20 Mar 2019.

Vancouver:

Nelson BL. Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility. [Internet] [Masters thesis]. Oregon State University; 2009. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/11999.

Council of Science Editors:

Nelson BL. Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility. [Masters Thesis]. Oregon State University; 2009. Available from: http://hdl.handle.net/1957/11999

14. 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

Oregon State University is designed to authenticate safety analysis efforts in the… …that will be undertaken by Oregon State University and NuScale Power Inc. will… …Description At Oregon State University, a new integral reactor test facility has been prepared by… 

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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 20, 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. 20 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 20]. 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

15. Jackson, R. Brian. An experimental study of laminarization induced by acceleration and curvature.

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

 The Generation IV Very High Temperature Reactor (VHTR) design is being actively studied in various countries for application due to its inherent passive safe design,… (more)

Subjects/Keywords: Turbulent Boundary Layer; Turbulent boundary layer

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APA (6th Edition):

Jackson, R. B. (2012). An experimental study of laminarization induced by acceleration and curvature. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/31676

Chicago Manual of Style (16th Edition):

Jackson, R Brian. “An experimental study of laminarization induced by acceleration and curvature.” 2012. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/31676.

MLA Handbook (7th Edition):

Jackson, R Brian. “An experimental study of laminarization induced by acceleration and curvature.” 2012. Web. 20 Mar 2019.

Vancouver:

Jackson RB. An experimental study of laminarization induced by acceleration and curvature. [Internet] [Doctoral dissertation]. Oregon State University; 2012. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/31676.

Council of Science Editors:

Jackson RB. An experimental study of laminarization induced by acceleration and curvature. [Doctoral Dissertation]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/31676

16. Lee, Dongyoung. Flow Dynamics and Condensation of Film Flows in Small Modular Reactors.

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

 There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and… (more)

Subjects/Keywords: Film flow dynamics; Nuclear reactors  – Safety measures

…Commission ODE Ordinary Differential Equation OSU Oregon State University PRHRS Passive… 

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APA (6th Edition):

Lee, D. (2015). Flow Dynamics and Condensation of Film Flows in Small Modular Reactors. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/56346

Chicago Manual of Style (16th Edition):

Lee, Dongyoung. “Flow Dynamics and Condensation of Film Flows in Small Modular Reactors.” 2015. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/56346.

MLA Handbook (7th Edition):

Lee, Dongyoung. “Flow Dynamics and Condensation of Film Flows in Small Modular Reactors.” 2015. Web. 20 Mar 2019.

Vancouver:

Lee D. Flow Dynamics and Condensation of Film Flows in Small Modular Reactors. [Internet] [Doctoral dissertation]. Oregon State University; 2015. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/56346.

Council of Science Editors:

Lee D. Flow Dynamics and Condensation of Film Flows in Small Modular Reactors. [Doctoral Dissertation]. Oregon State University; 2015. Available from: http://hdl.handle.net/1957/56346


Oregon State University

17. Welter, Kent B. Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch.

Degree: MS, Nuclear Engineering, 2001, Oregon State University

 A literature review of current phase separation publications was conducted. Data sets were collected and compiled into a Two-Phase Flow Separation Database. Examination of this… (more)

Subjects/Keywords: Two-phase flow  – Mathematical models

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APA (6th Edition):

Welter, K. B. (2001). Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/30753

Chicago Manual of Style (16th Edition):

Welter, Kent B. “Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch.” 2001. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/30753.

MLA Handbook (7th Edition):

Welter, Kent B. “Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch.” 2001. Web. 20 Mar 2019.

Vancouver:

Welter KB. Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch. [Internet] [Masters thesis]. Oregon State University; 2001. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/30753.

Council of Science Editors:

Welter KB. Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch. [Masters Thesis]. Oregon State University; 2001. Available from: http://hdl.handle.net/1957/30753


Oregon State University

18. Welter, Kent B. Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe.

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

 Under simulated accident conditions, tees in the primary coolant loop of a Pressurized Water Reactor (PWR) can deviate from their original design purpose and become… (more)

Subjects/Keywords: Pressurized water reactors  – Loss of coolant

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APA (6th Edition):

Welter, K. B. (2002). Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/30756

Chicago Manual of Style (16th Edition):

Welter, Kent B. “Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe.” 2002. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/30756.

MLA Handbook (7th Edition):

Welter, Kent B. “Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe.” 2002. Web. 20 Mar 2019.

Vancouver:

Welter KB. Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe. [Internet] [Doctoral dissertation]. Oregon State University; 2002. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/30756.

Council of Science Editors:

Welter KB. Liquid entrainment at an upward oriented vertical branch line from a horizontal pipe. [Doctoral Dissertation]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/30756


Oregon State University

19. McCreary, David M. Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters.

Degree: MS, Nuclear Engineering, 2000, Oregon State University

 This thesis examines two techniques for measuring two-phase flow parameters in an air/water system using intrusive conductivity probes. Specifically, the theoretical derivation for measuring void… (more)

Subjects/Keywords: Two-phase flow

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APA (6th Edition):

McCreary, D. M. (2000). Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/32921

Chicago Manual of Style (16th Edition):

McCreary, David M. “Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters.” 2000. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/32921.

MLA Handbook (7th Edition):

McCreary, David M. “Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters.” 2000. Web. 20 Mar 2019.

Vancouver:

McCreary DM. Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters. [Internet] [Masters thesis]. Oregon State University; 2000. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/32921.

Council of Science Editors:

McCreary DM. Design and testing of intrustive conductivity probes for the measurement of two-phase flow parameters. [Masters Thesis]. Oregon State University; 2000. Available from: http://hdl.handle.net/1957/32921


Oregon State University

20. Lee, Dongyoung. Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor.

Degree: MS, Nuclear Engineering, 2006, Oregon State University

 Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is being considered as the ideal design for a Next Generation Nuclear Plant (NGNP).… (more)

Subjects/Keywords: Gas cooled reactors  – Cooling

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APA (6th Edition):

Lee, D. (2006). Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/22694

Chicago Manual of Style (16th Edition):

Lee, Dongyoung. “Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor.” 2006. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/22694.

MLA Handbook (7th Edition):

Lee, Dongyoung. “Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor.” 2006. Web. 20 Mar 2019.

Vancouver:

Lee D. Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor. [Internet] [Masters thesis]. Oregon State University; 2006. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/22694.

Council of Science Editors:

Lee D. Analytical and numerical analysis of natural circulation for reactor cavity cooling system in gas cooled reactor. [Masters Thesis]. Oregon State University; 2006. Available from: http://hdl.handle.net/1957/22694


Oregon State University

21. Kim, Dong-Wan. A unified model of one-dimension two-fluid horizontal flows and its stability analysis.

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

 An improved version of the one-dimensional horizontal two-fluid flow model has been developed by incorporating physical terms for gravity and local void fraction profiles. Introduction… (more)

Subjects/Keywords: One-D two-fluid flow; Two-phase flow  – Mathematical models

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APA (6th Edition):

Kim, D. (2007). A unified model of one-dimension two-fluid horizontal flows and its stability analysis. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/7743

Chicago Manual of Style (16th Edition):

Kim, Dong-Wan. “A unified model of one-dimension two-fluid horizontal flows and its stability analysis.” 2007. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/7743.

MLA Handbook (7th Edition):

Kim, Dong-Wan. “A unified model of one-dimension two-fluid horizontal flows and its stability analysis.” 2007. Web. 20 Mar 2019.

Vancouver:

Kim D. A unified model of one-dimension two-fluid horizontal flows and its stability analysis. [Internet] [Doctoral dissertation]. Oregon State University; 2007. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/7743.

Council of Science Editors:

Kim D. A unified model of one-dimension two-fluid horizontal flows and its stability analysis. [Doctoral Dissertation]. Oregon State University; 2007. Available from: http://hdl.handle.net/1957/7743


Oregon State University

22. Sabharwall, Piyush. Effects of fluid axial conduction on liquid metal natural circulation and linear stability.

Degree: MS, Nuclear Engineering, 2004, Oregon State University

 The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through non-dimensional analysis, steady-state assessment, and… (more)

Subjects/Keywords: Liquid metal cooled reactors  – Cooling

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APA (6th Edition):

Sabharwall, P. (2004). Effects of fluid axial conduction on liquid metal natural circulation and linear stability. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/22690

Chicago Manual of Style (16th Edition):

Sabharwall, Piyush. “Effects of fluid axial conduction on liquid metal natural circulation and linear stability.” 2004. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/22690.

MLA Handbook (7th Edition):

Sabharwall, Piyush. “Effects of fluid axial conduction on liquid metal natural circulation and linear stability.” 2004. Web. 20 Mar 2019.

Vancouver:

Sabharwall P. Effects of fluid axial conduction on liquid metal natural circulation and linear stability. [Internet] [Masters thesis]. Oregon State University; 2004. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/22690.

Council of Science Editors:

Sabharwall P. Effects of fluid axial conduction on liquid metal natural circulation and linear stability. [Masters Thesis]. Oregon State University; 2004. Available from: http://hdl.handle.net/1957/22690


Oregon State University

23. Antoine, Stephanie Y. L. Antoine. The study of cold leg thermal stratification in APEX-CE.

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

 This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a… (more)

Subjects/Keywords: Thermal stresses

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APA (6th Edition):

Antoine, S. Y. L. A. (2002). The study of cold leg thermal stratification in APEX-CE. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/29718

Chicago Manual of Style (16th Edition):

Antoine, Stephanie Y L Antoine. “The study of cold leg thermal stratification in APEX-CE.” 2002. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/29718.

MLA Handbook (7th Edition):

Antoine, Stephanie Y L Antoine. “The study of cold leg thermal stratification in APEX-CE.” 2002. Web. 20 Mar 2019.

Vancouver:

Antoine SYLA. The study of cold leg thermal stratification in APEX-CE. [Internet] [Masters thesis]. Oregon State University; 2002. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/29718.

Council of Science Editors:

Antoine SYLA. The study of cold leg thermal stratification in APEX-CE. [Masters Thesis]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/29718


Oregon State University

24. Abel, Kent C. Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification.

Degree: PhD, Nuclear Engineering, 2005, Oregon State University

 The next generation of nuclear safety analysis computer codes will require detailed modeling of two-phase fluid flow. The most complete and fundamental model used for… (more)

Subjects/Keywords: Two-phase flow  – Mathematical models

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APA (6th Edition):

Abel, K. C. (2005). Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/28886

Chicago Manual of Style (16th Edition):

Abel, Kent C. “Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification.” 2005. Doctoral Dissertation, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/28886.

MLA Handbook (7th Edition):

Abel, Kent C. “Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification.” 2005. Web. 20 Mar 2019.

Vancouver:

Abel KC. Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification. [Internet] [Doctoral dissertation]. Oregon State University; 2005. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/28886.

Council of Science Editors:

Abel KC. Stability improvement of the one-dimensional two-fluid model for horizontal two-phase flow with model unification. [Doctoral Dissertation]. Oregon State University; 2005. Available from: http://hdl.handle.net/1957/28886


Oregon State University

25. Tang, Hong. Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility.

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

 Natural convection provides a means for circulating fluids without the use of pumps. This type of system is of great interest for a wide variety… (more)

Subjects/Keywords: Heat  – Convection; Natural

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APA (6th Edition):

Tang, H. (2002). Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/32151

Chicago Manual of Style (16th Edition):

Tang, Hong. “Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility.” 2002. Masters Thesis, Oregon State University. Accessed March 20, 2019. http://hdl.handle.net/1957/32151.

MLA Handbook (7th Edition):

Tang, Hong. “Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility.” 2002. Web. 20 Mar 2019.

Vancouver:

Tang H. Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility. [Internet] [Masters thesis]. Oregon State University; 2002. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1957/32151.

Council of Science Editors:

Tang H. Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility. [Masters Thesis]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/32151

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