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You searched for +publisher:"The Ohio State University" +contributor:("SUN, XIAODONG"). Showing records 1 – 21 of 21 total matches.

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The Ohio State University

1. Niehus, Mark T. An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows.

Degree: MS, Nuclear Engineering, 2008, The Ohio State University

 An investigative experimental study was conducted on the cross correlation velocity measurement method in turbulent single-phase air and water pipe flows. T-type and K-type fast… (more)

Subjects/Keywords: Fluid Dynamics; Mechanical Engineering; Fiber Optic Temperature Sensors; Cross Correlation; Flow Velocity Measurment

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APA (6th Edition):

Niehus, M. T. (2008). An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1213385038

Chicago Manual of Style (16th Edition):

Niehus, Mark T. “An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows.” 2008. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213385038.

MLA Handbook (7th Edition):

Niehus, Mark T. “An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows.” 2008. Web. 19 Mar 2019.

Vancouver:

Niehus MT. An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213385038.

Council of Science Editors:

Niehus MT. An Experimental Study of Temperature Sensor Noise Analysis in Evaluating the Velocity of Single-Phase Air and Water Flows. [Masters Thesis]. The Ohio State University; 2008. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213385038


The Ohio State University

2. Mylavarapu, Sai K. Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors.

Degree: MS, Nuclear Engineering, 2008, The Ohio State University

 The U.S. Department of Energy’s Generation IV Program has generated considerable interest for High-Temperature Gas-Cooled Reactors (HTGR), in particular, the Very-High-Temperature Reactor (VHTR). VHTR is… (more)

Subjects/Keywords: Mechanical Engineering; PCHE; Compact Heat Exchanger; Diffusion bonded heat exchanger; Photochemical machining

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APA (6th Edition):

Mylavarapu, S. K. (2008). Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1228150070

Chicago Manual of Style (16th Edition):

Mylavarapu, Sai K. “Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors.” 2008. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1228150070.

MLA Handbook (7th Edition):

Mylavarapu, Sai K. “Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors.” 2008. Web. 19 Mar 2019.

Vancouver:

Mylavarapu SK. Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1228150070.

Council of Science Editors:

Mylavarapu SK. Development of Compact Heat Exchangers for Very High-Temperature Gas-Cooled Reactors. [Masters Thesis]. The Ohio State University; 2008. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1228150070


The Ohio State University

3. Wang, Xia. Simulations of Two-phase Flows Using Interfacial Area Transport Equation.

Degree: PhD, Nuclear Engineering, 2010, The Ohio State University

 The current study focuses on providing a reliable computational fluid dynamics (CFD) tool for two-phase flow simulations, which is capable of capturing dynamic changes of… (more)

Subjects/Keywords: Engineering; two-phase flow simulation; two-fluid model; interfacial area transport equation; interfacial force; well-posedness

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APA (6th Edition):

Wang, X. (2010). Simulations of Two-phase Flows Using Interfacial Area Transport Equation. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1282066341

Chicago Manual of Style (16th Edition):

Wang, Xia. “Simulations of Two-phase Flows Using Interfacial Area Transport Equation.” 2010. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1282066341.

MLA Handbook (7th Edition):

Wang, Xia. “Simulations of Two-phase Flows Using Interfacial Area Transport Equation.” 2010. Web. 19 Mar 2019.

Vancouver:

Wang X. Simulations of Two-phase Flows Using Interfacial Area Transport Equation. [Internet] [Doctoral dissertation]. The Ohio State University; 2010. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1282066341.

Council of Science Editors:

Wang X. Simulations of Two-phase Flows Using Interfacial Area Transport Equation. [Doctoral Dissertation]. The Ohio State University; 2010. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1282066341


The Ohio State University

4. Glosup, Richard Edwin. Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory.

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

  The U.S. Department of Energy’s (DOE) Office of Nuclear Energy is actively pursuing design research related to Generation IV nuclear reactors for near term… (more)

Subjects/Keywords: Energy; Engineering; Nuclear Engineering; High-temperature; characterization

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APA (6th Edition):

Glosup, R. E. (2011). Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1313248382

Chicago Manual of Style (16th Edition):

Glosup, Richard Edwin. “Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory.” 2011. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1313248382.

MLA Handbook (7th Edition):

Glosup, Richard Edwin. “Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory.” 2011. Web. 19 Mar 2019.

Vancouver:

Glosup RE. Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory. [Internet] [Masters thesis]. The Ohio State University; 2011. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1313248382.

Council of Science Editors:

Glosup RE. Characterization of the High-Temperature Helium Facility in the Thermal Hydraulics Laboratory. [Masters Thesis]. The Ohio State University; 2011. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1313248382


The Ohio State University

5. Doup, Benjamin. Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model.

Degree: PhD, Nuclear Engineering, 2014, The Ohio State University

 Current reactor safety analysis codes, such as RELAP5, TRACE, and CATHARE, use flow regime maps or flow regime transition criteria that were developed for static… (more)

Subjects/Keywords: Nuclear Engineering; Two-Phase Flow, Bubble Dynamics, Interfacial Area Transport, Flow Regime Transition Model

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APA (6th Edition):

Doup, B. (2014). Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1409031809

Chicago Manual of Style (16th Edition):

Doup, Benjamin. “Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model.” 2014. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1409031809.

MLA Handbook (7th Edition):

Doup, Benjamin. “Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model.” 2014. Web. 19 Mar 2019.

Vancouver:

Doup B. Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model. [Internet] [Doctoral dissertation]. The Ohio State University; 2014. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1409031809.

Council of Science Editors:

Doup B. Methodology Development of a Gas-Liquid Dynamic Flow Regime Transition Model. [Doctoral Dissertation]. The Ohio State University; 2014. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1409031809


The Ohio State University

6. Wegman, Kevin R. Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility.

Degree: MS, Nuclear Engineering, 2016, The Ohio State University

 The U.S. Department of Energy’s Generation IV Program has identified six advanced reactor technologies to be investigated for possible deployment in both energy and process… (more)

Subjects/Keywords: Nuclear Engineering; Printed Circuit Heat Exchanger; PCHE; COMSOL Multiphysics; CFD

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APA (6th Edition):

Wegman, K. R. (2016). Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1461266010

Chicago Manual of Style (16th Edition):

Wegman, Kevin R. “Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility.” 2016. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1461266010.

MLA Handbook (7th Edition):

Wegman, Kevin R. “Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility.” 2016. Web. 19 Mar 2019.

Vancouver:

Wegman KR. Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1461266010.

Council of Science Editors:

Wegman KR. Numerical Modeling of a Printed Circuit Heat Exchanger Based on Experimental Results from the High-Temperature Helium Test Facility. [Masters Thesis]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1461266010


The Ohio State University

7. Lu, Qiuping. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.

Degree: PhD, Nuclear Engineering, 2016, The Ohio State University

 Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines coated particle fuel… (more)

Subjects/Keywords: Nuclear Engineering; FHR, DRACS, passive decay heat removal, LTDF, HTDF

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APA (6th Edition):

Lu, Q. (2016). Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389

Chicago Manual of Style (16th Edition):

Lu, Qiuping. “Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.” 2016. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389.

MLA Handbook (7th Edition):

Lu, Qiuping. “Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs.” 2016. Web. 19 Mar 2019.

Vancouver:

Lu Q. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. [Internet] [Doctoral dissertation]. The Ohio State University; 2016. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389.

Council of Science Editors:

Lu Q. Design, Testing and Modeling of the Direct Reactor Auxiliary Cooling System for FHRs. [Doctoral Dissertation]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462544389


The Ohio State University

8. Lin, Hsun-Chia. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.

Degree: MS, Nuclear Engineering, 2016, The Ohio State University

 Direct Reactor Auxiliary Cooling System (DRACS), a passive safety system proposed for Fluoride-salt-cooled High-temperature Reactors (FHRs), is driven by natural convection/circulation to remove the decay… (more)

Subjects/Keywords: Nuclear Engineering; DRACS, FHR, RELAP5, AHTR

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APA (6th Edition):

Lin, H. (2016). RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408

Chicago Manual of Style (16th Edition):

Lin, Hsun-Chia. “RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.” 2016. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408.

MLA Handbook (7th Edition):

Lin, Hsun-Chia. “RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities.” 2016. Web. 19 Mar 2019.

Vancouver:

Lin H. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408.

Council of Science Editors:

Lin H. RELAP5 Model Benchmark for Thermal Performance of DRACS Test Facilities. [Masters Thesis]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462889408

9. Zhang, Xiaoqin. THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN.

Degree: MS, Nuclear Engineering, 2016, The Ohio State University

 Coupling the s-CO2 Brayton cycle to the advanced nuclear reactors generally requires an intermediate heat exchanger (IHX). From an economic viewpoint, it is important to… (more)

Subjects/Keywords: Nuclear Engineering; Intermediate Heat Exchanger, Printed Circuit Heat Exchanger, Multi-Objective Optimization, Genetic Algorithms, Stress Analysis

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APA (6th Edition):

Zhang, X. (2016). THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1462891005

Chicago Manual of Style (16th Edition):

Zhang, Xiaoqin. “THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN.” 2016. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1462891005.

MLA Handbook (7th Edition):

Zhang, Xiaoqin. “THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN.” 2016. Web. 19 Mar 2019.

Vancouver:

Zhang X. THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462891005.

Council of Science Editors:

Zhang X. THERMAL-ECONOMIC OPTIMIZATION AND STRUCTURAL EVALUATION FOR AN ADVANCED INTERMEDIATE HEAT EXCHANGER DESIGN. [Masters Thesis]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1462891005


The Ohio State University

10. Yee, Shannon K. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.

Degree: MS, Nuclear Engineering, 2008, The Ohio State University

 Policy decisions regarding the direction of nuclear power utilize sophisticated fuel cycle models. Both static and dynamic models are used to determine how a proposed… (more)

Subjects/Keywords: Engineering; Mechanical Engineering; Nuclear Chemistry; Nuclear Physics; Physics; fuel cycle; spent nuclear fuel; nuclear fuel recycling; transmutation

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APA (6th Edition):

Yee, S. K. (2008). Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425

Chicago Manual of Style (16th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

MLA Handbook (7th Edition):

Yee, Shannon K. “Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel.” 2008. Web. 19 Mar 2019.

Vancouver:

Yee SK. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425.

Council of Science Editors:

Yee SK. Nuclear Fuel Cycle Modeling Approaches For Recycling And Transmutation Of Spent Nuclear Fuel. [Masters Thesis]. The Ohio State University; 2008. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1213905425


The Ohio State University

11. Figley, Justin T. Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors.

Degree: MS, Nuclear Engineering, 2009, The Ohio State University

 Very High Temperature Reactors (VHTRs) operate at high temperatures (1,173-1,223 K) and require intermediate heat exchangers to transfer thermal energy to a hydrogen production plant… (more)

Subjects/Keywords: Energy; Engineering; Mechanical Engineering; Intermediate Heat Exchanger; Thermal Hydraulics; VHTR; Printer Circuit Heat Exchanger; PCHE

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APA (6th Edition):

Figley, J. T. (2009). Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1244036854

Chicago Manual of Style (16th Edition):

Figley, Justin T. “Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors.” 2009. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1244036854.

MLA Handbook (7th Edition):

Figley, Justin T. “Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors.” 2009. Web. 19 Mar 2019.

Vancouver:

Figley JT. Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1244036854.

Council of Science Editors:

Figley JT. Numerical Modeling and Performance Analysis of Printed Circuit Heat Exchanger for Very High-Temperature Reactors. [Masters Thesis]. The Ohio State University; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1244036854


The Ohio State University

12. Abejon Orzaez, Jorge. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.

Degree: MS, Nuclear Engineering, 2009, The Ohio State University

 The objective of this research is to, based on the original design for the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), develop an MCNPX model… (more)

Subjects/Keywords: Engineering; Nuclear Physics; Neutronics; advanced high temperature reactor; criticality

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APA (6th Edition):

Abejon Orzaez, J. (2009). Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558

Chicago Manual of Style (16th Edition):

Abejon Orzaez, Jorge. “Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.” 2009. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.

MLA Handbook (7th Edition):

Abejon Orzaez, Jorge. “Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor.” 2009. Web. 19 Mar 2019.

Vancouver:

Abejon Orzaez J. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558.

Council of Science Editors:

Abejon Orzaez J. Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor. [Masters Thesis]. The Ohio State University; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1238045558

13. Ham, Tae Kyu. CFD Analyses of Air-Ingress Accident for VHTRs.

Degree: PhD, Nuclear Engineering, 2014, The Ohio State University

 The Very High Temperature Reactor (VHTR) is one of six proposed Generation-IV concepts for the next generation of nuclear powered plants. The VHTR is advantageous… (more)

Subjects/Keywords: Nuclear Engineering; Air-ingress, CFD, Uncertainty quantification

…Aerospace Engineering, The Ohio State University Fields of Study Major Field: Nuclear… 

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APA (6th Edition):

Ham, T. K. (2014). CFD Analyses of Air-Ingress Accident for VHTRs. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1406207976

Chicago Manual of Style (16th Edition):

Ham, Tae Kyu. “CFD Analyses of Air-Ingress Accident for VHTRs.” 2014. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1406207976.

MLA Handbook (7th Edition):

Ham, Tae Kyu. “CFD Analyses of Air-Ingress Accident for VHTRs.” 2014. Web. 19 Mar 2019.

Vancouver:

Ham TK. CFD Analyses of Air-Ingress Accident for VHTRs. [Internet] [Doctoral dissertation]. The Ohio State University; 2014. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1406207976.

Council of Science Editors:

Ham TK. CFD Analyses of Air-Ingress Accident for VHTRs. [Doctoral Dissertation]. The Ohio State University; 2014. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1406207976

14. Wu, Xiao. Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems.

Degree: MS, Nuclear Engineering, 2016, The Ohio State University

 The Fluoride salt-cooled High-temperature Reactor (FHR) is a Generation-IV molten salt reactor. However, tritium generation from neutron activation of the primary coolant FLiBe (a mixture… (more)

Subjects/Keywords: Nuclear Engineering

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APA (6th Edition):

Wu, X. (2016). Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907

Chicago Manual of Style (16th Edition):

Wu, Xiao. “Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems.” 2016. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907.

MLA Handbook (7th Edition):

Wu, Xiao. “Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems.” 2016. Web. 19 Mar 2019.

Vancouver:

Wu X. Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems. [Internet] [Masters thesis]. The Ohio State University; 2016. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907.

Council of Science Editors:

Wu X. Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems. [Masters Thesis]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907

15. Mylavarapu, Sai Kiran. Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility.

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

  Very High-Temperature Reactor (VHTR) is a leading candidate for the U.S. Department of Energy’s Next Generation Nuclear Power Plant (NGNP) project. It is a… (more)

Subjects/Keywords: Nuclear Engineering; Heat Exchangers; Diffusion Bonding; PCHE; High-Temperature Helium Test Facility; HTHF

…M.S. Nuclear Engineering, The Ohio State University 2007 to present… …Graduate Research Associate, Nuclear Engineering Program, The Ohio State University Journal… …by the Ohio State University [1.6]. When this research started about 5 years ago… …fabricated at The Ohio State University. The PCHE model dimensions are representative of the PCHEs… …High Temperature Reactors," M.S. Thesis, The Ohio State University, Columbus, OH. [… 

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APA (6th Edition):

Mylavarapu, S. K. (2011). Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1321996306

Chicago Manual of Style (16th Edition):

Mylavarapu, Sai Kiran. “Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility.” 2011. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1321996306.

MLA Handbook (7th Edition):

Mylavarapu, Sai Kiran. “Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility.” 2011. Web. 19 Mar 2019.

Vancouver:

Mylavarapu SK. Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility. [Internet] [Doctoral dissertation]. The Ohio State University; 2011. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1321996306.

Council of Science Editors:

Mylavarapu SK. Design, Fabrication, Performance Testing, and Modeling of Diffusion Bonded Compact Heat Exchangers in a High-Temperature Helium Test Facility. [Doctoral Dissertation]. The Ohio State University; 2011. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1321996306

16. Zhou, Xinquan. Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions.

Degree: PhD, Mechanical Engineering, 2014, The Ohio State University

 The current work focuses on the measurement and modeling of liquid-phase turbulence in adiabatic air-water two-phase flow with a relatively wide range of void fractions.… (more)

Subjects/Keywords: Mechanical Engineering; Two-phase flow; PIV; Turbulence; Void fraction; Measurement; Modeling; Nuclear Engineering

…M.S. Mechanical Engineering, The Ohio State University 2009 to present… …Graduate Research Assistant, Department of Mechanical and Aerospace Engineering, The Ohio State… …University Publications 1. B. Doup, X. Zhou, I. H. Kim, X. Sun, “Local axial relative velocity… 

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APA (6th Edition):

Zhou, X. (2014). Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1406210359

Chicago Manual of Style (16th Edition):

Zhou, Xinquan. “Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions.” 2014. Doctoral Dissertation, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1406210359.

MLA Handbook (7th Edition):

Zhou, Xinquan. “Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions.” 2014. Web. 19 Mar 2019.

Vancouver:

Zhou X. Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions. [Internet] [Doctoral dissertation]. The Ohio State University; 2014. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1406210359.

Council of Science Editors:

Zhou X. Measurement and Modeling of the Liquid-phase Turbulence in Adiabatic Air-water Two-phase Flows with a Wide Range of Void Fractions. [Doctoral Dissertation]. The Ohio State University; 2014. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1406210359

17. Adams , Imani Noel. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.

Degree: MS, Mechanical Engineering, 2013, The Ohio State University

  The Direct Reactor Auxiliary Cooling System (DRACS) is a passive heat removal system proposed for Fluoride Salt-Cooled High-Temperature Reactors (FHRs). It features three coupled… (more)

Subjects/Keywords: Mechanical Engineering; Nuclear Engineering; DRACS; FHR

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APA (6th Edition):

Adams , I. N. (2013). Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705

Chicago Manual of Style (16th Edition):

Adams , Imani Noel. “Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.” 2013. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705.

MLA Handbook (7th Edition):

Adams , Imani Noel. “Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors.” 2013. Web. 19 Mar 2019.

Vancouver:

Adams IN. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705.

Council of Science Editors:

Adams IN. Comprehensive Analysis of a Scaled-Down Low-Temperature Direct Reactor Auxiliary Cooling System for Fluoride Salt-Cooled High-Temperature Reactors. [Masters Thesis]. The Ohio State University; 2013. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1366464705

18. Lv, Qiuping. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.

Degree: MS, Nuclear Engineering, 2013, The Ohio State University

 The Advanced High Temperature Reactor (AHTR) is one of the advanced rector concepts that have been proposed for Gen IV reactors. The AHTR combines four… (more)

Subjects/Keywords: Nuclear Engineering; AHTR; DRACS; prototypic design; scaling

…Graduate Fellow, Nuclear Engineering Program, The Ohio State University 2011 to present… …Graduate Research Associate, Nuclear Engineering Program, The Ohio State University Publications… 

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APA (6th Edition):

Lv, Q. (2013). Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725

Chicago Manual of Style (16th Edition):

Lv, Qiuping. “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.” 2013. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725.

MLA Handbook (7th Edition):

Lv, Qiuping. “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs.” 2013. Web. 19 Mar 2019.

Vancouver:

Lv Q. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725.

Council of Science Editors:

Lv Q. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs. [Masters Thesis]. The Ohio State University; 2013. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1357312725

19. Chen, Minghui. DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER.

Degree: MS, Nuclear Engineering, 2015, The Ohio State University

 One of the very-high-temperature reactor (VHTR) missions is to produce electricity and/or to provide process heat for applications with high efficiency. The electricity generation or… (more)

Subjects/Keywords: Engineering; Nuclear Engineering; Energy; Mechanical Engineering; PCHE, thermal-hydraulic performance, compact heat exchangers, high-temperature helium facility, VHTR, dynamic response

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APA (6th Edition):

Chen, M. (2015). DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1431072434

Chicago Manual of Style (16th Edition):

Chen, Minghui. “DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER.” 2015. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1431072434.

MLA Handbook (7th Edition):

Chen, Minghui. “DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER.” 2015. Web. 19 Mar 2019.

Vancouver:

Chen M. DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER. [Internet] [Masters thesis]. The Ohio State University; 2015. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1431072434.

Council of Science Editors:

Chen M. DESIGN, FABRICATION, TESTING, AND MODELING OF A HIGH-TEMPERATURE PRINTED CIRCUIT HEAT EXCHANGER. [Masters Thesis]. The Ohio State University; 2015. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1431072434

20. Doup, Benjamin. Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows.

Degree: MS, Nuclear Engineering, 2012, The Ohio State University

 The objective of this research is to help in the development of a dynamic flow regime transition model by providing accurate experimental two-phase flow data… (more)

Subjects/Keywords: Nuclear Engineering; two-phase flow; flow structure; flow development

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APA (6th Edition):

Doup, B. (2012). Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1332514704

Chicago Manual of Style (16th Edition):

Doup, Benjamin. “Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows.” 2012. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1332514704.

MLA Handbook (7th Edition):

Doup, Benjamin. “Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows.” 2012. Web. 19 Mar 2019.

Vancouver:

Doup B. Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1332514704.

Council of Science Editors:

Doup B. Experimental Investigation of Flow Structure Development in Air-water Two-phase Flows. [Masters Thesis]. The Ohio State University; 2012. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1332514704

21. Arcilesi, David J., Jr. Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident.

Degree: MS, Nuclear Engineering, 2012, The Ohio State University

 A critical event in the safety analysis of the Very High-temperature Gas-cooled Reactor (VHTR) is a loss-of-coolant accident (LOCA). This accident is initiated, in its… (more)

Subjects/Keywords: Nuclear Engineering; VHTR; Air-ingress Accident; Nuclear Engineering; high temperature gas-cooled reactor

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APA (6th Edition):

Arcilesi, David J., J. (2012). Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1338387523

Chicago Manual of Style (16th Edition):

Arcilesi, David J., Jr. “Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident.” 2012. Masters Thesis, The Ohio State University. Accessed March 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1338387523.

MLA Handbook (7th Edition):

Arcilesi, David J., Jr. “Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident.” 2012. Web. 19 Mar 2019.

Vancouver:

Arcilesi, David J. J. Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Mar 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1338387523.

Council of Science Editors:

Arcilesi, David J. J. Developmental Analysis and Design of a Scaled-down Test Facility for a VHTR Air-ingress Accident. [Masters Thesis]. The Ohio State University; 2012. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1338387523

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