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You searched for +publisher:"McMaster University" +contributor:("Novog, David"). Showing records 1 – 21 of 21 total matches.

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McMaster University

1. Younan, Simon. Comparative study of accident-tolerant fuel for a CANDU lattice.

Degree: MASc, 2017, McMaster University

McMaster University MASTER OF APPLIED SCIENCES (2017) Hamilton, Ontario (Engineering Physics) TITLE: Comparative study of accident-tolerant fuel for a CANDU lattice AUTHOR: Simon Younan, B.Eng.… (more)

Subjects/Keywords: nuclear engineering; reactor physics; CANDU; accident-tolerant fuel; Serpent 2; Monte Carlo; accident-tolerant cladding

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APA (6th Edition):

Younan, S. (2017). Comparative study of accident-tolerant fuel for a CANDU lattice. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/22194

Chicago Manual of Style (16th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/22194.

MLA Handbook (7th Edition):

Younan, Simon. “Comparative study of accident-tolerant fuel for a CANDU lattice.” 2017. Web. 15 Feb 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/22194.

Council of Science Editors:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22194


McMaster University

2. Zhou, Feng. Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors.

Degree: PhD, 2018, McMaster University

 Since the Fukushima Daiichi nuclear accident, there have been ongoing efforts to enhance the modelling capabilities for severe accidents in nuclear power plants. The primary… (more)

Subjects/Keywords: CANDU; Severe Accidents; Station Blackout; RELAP/SCDAPSIM

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APA (6th Edition):

Zhou, F. (2018). Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/23471

Chicago Manual of Style (16th Edition):

Zhou, Feng. “Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors.” 2018. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/23471.

MLA Handbook (7th Edition):

Zhou, Feng. “Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors.” 2018. Web. 15 Feb 2019.

Vancouver:

Zhou F. Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/23471.

Council of Science Editors:

Zhou F. Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors. [Doctoral Dissertation]. McMaster University; 2018. Available from: http://hdl.handle.net/11375/23471


McMaster University

3. Sabouri, Pouya. Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant.

Degree: MASc, 2010, McMaster University

A RELAP5 input model representative of a 900 MW CANDU plant was created. Due to the one dimensional nature of the code, complex plant… (more)

Subjects/Keywords: Engineering Physics; Engineering Physics

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APA (6th Edition):

Sabouri, P. (2010). Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/9216

Chicago Manual of Style (16th Edition):

Sabouri, Pouya. “Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant.” 2010. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/9216.

MLA Handbook (7th Edition):

Sabouri, Pouya. “Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant.” 2010. Web. 15 Feb 2019.

Vancouver:

Sabouri P. Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant. [Internet] [Masters thesis]. McMaster University; 2010. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/9216.

Council of Science Editors:

Sabouri P. Large LOCA BEAU Analysis of a Generic 900MW CANDU Plant. [Masters Thesis]. McMaster University; 2010. Available from: http://hdl.handle.net/11375/9216


McMaster University

4. Wu, Yang. Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios.

Degree: MASc, 2014, McMaster University

This Study is performed to assess the Canadian pre-conceptual SCWR design for Loss of Flow events leading to degraded cooling conditions and to assess the… (more)

Subjects/Keywords: SCWR; LOFA

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APA (6th Edition):

Wu, Y. (2014). Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/16434

Chicago Manual of Style (16th Edition):

Wu, Yang. “Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios.” 2014. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/16434.

MLA Handbook (7th Edition):

Wu, Yang. “Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios.” 2014. Web. 15 Feb 2019.

Vancouver:

Wu Y. Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios. [Internet] [Masters thesis]. McMaster University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/16434.

Council of Science Editors:

Wu Y. Prediction of The Response of the Canadian Super Critical Water Reactor to Potential Loss of Forced Flow Scenarios. [Masters Thesis]. McMaster University; 2014. Available from: http://hdl.handle.net/11375/16434


McMaster University

5. Leung, Kenneth. Effect of Flow Blockages on Interfacial Area in Two-Phase Flows.

Degree: PhD, 2014, McMaster University

 The interfacial area between two fluid phases governs the rate which mass, momentum and energy can be exchanged. Modern approaches to calculating the evolution of… (more)

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APA (6th Edition):

Leung, K. (2014). Effect of Flow Blockages on Interfacial Area in Two-Phase Flows. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/16498

Chicago Manual of Style (16th Edition):

Leung, Kenneth. “Effect of Flow Blockages on Interfacial Area in Two-Phase Flows.” 2014. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/16498.

MLA Handbook (7th Edition):

Leung, Kenneth. “Effect of Flow Blockages on Interfacial Area in Two-Phase Flows.” 2014. Web. 15 Feb 2019.

Vancouver:

Leung K. Effect of Flow Blockages on Interfacial Area in Two-Phase Flows. [Internet] [Doctoral dissertation]. McMaster University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/16498.

Council of Science Editors:

Leung K. Effect of Flow Blockages on Interfacial Area in Two-Phase Flows. [Doctoral Dissertation]. McMaster University; 2014. Available from: http://hdl.handle.net/11375/16498


McMaster University

6. Gocmanac, Marko. Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment.

Degree: MASc, 2011, McMaster University

An experimental investigation of the physical feasibility of thermal creep failure of the Calandria Vessel under a severe accident load is presented in this… (more)

Subjects/Keywords: Critical Heat Flux Pool Boiling; Heat Transfer, Combustion; Nuclear Engineering; Heat Transfer, Combustion

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APA (6th Edition):

Gocmanac, M. (2011). Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11813

Chicago Manual of Style (16th Edition):

Gocmanac, Marko. “Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment.” 2011. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/11813.

MLA Handbook (7th Edition):

Gocmanac, Marko. “Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment.” 2011. Web. 15 Feb 2019.

Vancouver:

Gocmanac M. Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/11813.

Council of Science Editors:

Gocmanac M. Critical Heat Flux for a Downwards Facing Disk in a Subcooled Pool Boiling Environment. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11813


McMaster University

7. Salaun, Frédéric. Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling.

Degree: PhD, 2018, McMaster University

Canadian Nuclear Laboratories conceptualized a new reactor design to fulfill the goals set forth by the Generation IV International Forum. Unlike the traditional CANDU™, the… (more)

Subjects/Keywords: Nuclear Engineering

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APA (6th Edition):

Salaun, F. (2018). Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/23025

Chicago Manual of Style (16th Edition):

Salaun, Frédéric. “Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling.” 2018. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/23025.

MLA Handbook (7th Edition):

Salaun, Frédéric. “Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling.” 2018. Web. 15 Feb 2019.

Vancouver:

Salaun F. Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/23025.

Council of Science Editors:

Salaun F. Assessment and Optimization of the Canadian SCWR reactivity control systems through reactor physics and thermal-hydraulics coupling. [Doctoral Dissertation]. McMaster University; 2018. Available from: http://hdl.handle.net/11375/23025


McMaster University

8. Hollingshead, Christopher William. CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY.

Degree: MASc, 2017, McMaster University

Flow in the Moderator of a CANDU reactor can be very complex due to the interplay of convective and buoyant effects. Experiments have been performed… (more)

Subjects/Keywords: CFD; Turbulence; Moderator; CANDU; RANS; Manifold

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APA (6th Edition):

Hollingshead, C. W. (2017). CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/22167

Chicago Manual of Style (16th Edition):

Hollingshead, Christopher William. “CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY.” 2017. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/22167.

MLA Handbook (7th Edition):

Hollingshead, Christopher William. “CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY.” 2017. Web. 15 Feb 2019.

Vancouver:

Hollingshead CW. CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/22167.

Council of Science Editors:

Hollingshead CW. CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22167


McMaster University

9. Glanfield, Edward Matthew. Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR.

Degree: MASc, 2017, McMaster University

 The Canadian-designed Super-Critical Water-cooled Reactor (SCWR) has been in development since the early 2000s and has undergone many design changes since its initial conception. Initially… (more)

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APA (6th Edition):

Glanfield, E. M. (2017). Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/23073

Chicago Manual of Style (16th Edition):

Glanfield, Edward Matthew. “Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR.” 2017. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/23073.

MLA Handbook (7th Edition):

Glanfield, Edward Matthew. “Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR.” 2017. Web. 15 Feb 2019.

Vancouver:

Glanfield EM. Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/23073.

Council of Science Editors:

Glanfield EM. Lattice Physics Calculations for Alternative Fuels for the Canadian SCWR. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/23073


McMaster University

10. Moghrabi, Ahmad. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.

Degree: PhD, 2018, McMaster University

The Generation IV International Forum (GIF) has initiated an international collaboration for the research and development of the Generation IV future nuclear energy systems. The… (more)

Subjects/Keywords: Generation IV nuclear reactor; Canadian PT-SCWR; Advanced nuclear Energy system; Lattice physics phenomena; Energy group structure optimization; SCALE code; Uncertainty Analysis; Sensitivity Analysis; Transport Calcuations; Optimization and algorithm

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APA (6th Edition):

Moghrabi, A. (2018). INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/22886

Chicago Manual of Style (16th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/22886.

MLA Handbook (7th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Web. 15 Feb 2019.

Vancouver:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/22886.

Council of Science Editors:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Doctoral Dissertation]. McMaster University; 2018. Available from: http://hdl.handle.net/11375/22886


McMaster University

11. Hummel, David. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.

Degree: PhD, 2015, McMaster University

The Generation IV International Forum has established several goals for the next generation of nuclear energy systems, which are to be substantial improvements over contemporary… (more)

Subjects/Keywords: SCWR; Neutronics; Thermalhydraulics; Coupling

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APA (6th Edition):

Hummel, D. (2015). Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/18363

Chicago Manual of Style (16th Edition):

Hummel, David. “Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.” 2015. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/18363.

MLA Handbook (7th Edition):

Hummel, David. “Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor.” 2015. Web. 15 Feb 2019.

Vancouver:

Hummel D. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. [Internet] [Doctoral dissertation]. McMaster University; 2015. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/18363.

Council of Science Editors:

Hummel D. Coupled Neutronic-Thermalhydraulic Transient Behaviour of a Pressure Tube Type Supercritical Water-cooled Reactor. [Doctoral Dissertation]. McMaster University; 2015. Available from: http://hdl.handle.net/11375/18363


McMaster University

12. Lou, Mengmeng. LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4.

Degree: MASc, 2016, McMaster University

 Canada has participated in the Generation IV International Forum (GIF) collaboration in the area of Super Critical Water-cooled Reactors (SCWR). Similar to the current CANDU… (more)

Subjects/Keywords: Safety analysis; Canadian SCWR; LOCA

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APA (6th Edition):

Lou, M. (2016). LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/19137

Chicago Manual of Style (16th Edition):

Lou, Mengmeng. “LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4.” 2016. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/19137.

MLA Handbook (7th Edition):

Lou, Mengmeng. “LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4.” 2016. Web. 15 Feb 2019.

Vancouver:

Lou M. LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4. [Internet] [Masters thesis]. McMaster University; 2016. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/19137.

Council of Science Editors:

Lou M. LOSS OF COOLANT ACCIDENT SIMULATION FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR USING RELAP5/MOD4. [Masters Thesis]. McMaster University; 2016. Available from: http://hdl.handle.net/11375/19137


McMaster University

13. Ball, Matthew R. Uncertainty Analysis In Lattice Reactor Physics Calculations.

Degree: PhD, 2011, McMaster University

Comprehensive sensitivity and uncertainty analysis has been performed for light-water reactor and heavy-water reactor lattices using three techniques; adjoint-based sensitivity analysis, Monte Carlo sampling,… (more)

Subjects/Keywords: nuclear engineering; reactor physics; uncertainty analysis; covariance; cross-sections; resonance self-shielding; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Ball, M. R. (2011). Uncertainty Analysis In Lattice Reactor Physics Calculations. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/11609

Chicago Manual of Style (16th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Doctoral Dissertation, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/11609.

MLA Handbook (7th Edition):

Ball, Matthew R. “Uncertainty Analysis In Lattice Reactor Physics Calculations.” 2011. Web. 15 Feb 2019.

Vancouver:

Ball MR. Uncertainty Analysis In Lattice Reactor Physics Calculations. [Internet] [Doctoral dissertation]. McMaster University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/11609.

Council of Science Editors:

Ball MR. Uncertainty Analysis In Lattice Reactor Physics Calculations. [Doctoral Dissertation]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11609


McMaster University

14. McEwan, Curtis E. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.

Degree: MASc, 2013, McMaster University

Simulation plays a key role in nuclear reactor safety analysis and being able to assess the accuracy of results obtained by simulation increases their… (more)

Subjects/Keywords: Reactor Physics; Covariance; Uncertainty Analysis; Total Monte Carlo; Dilution; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

McEwan, C. E. (2013). Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/13396

Chicago Manual of Style (16th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/13396.

MLA Handbook (7th Edition):

McEwan, Curtis E. “Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations.” 2013. Web. 15 Feb 2019.

Vancouver:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/13396.

Council of Science Editors:

McEwan CE. Covariance in Multigroup and Few Group Reactor Physics Uncertainty Calculations. [Masters Thesis]. McMaster University; 2013. Available from: http://hdl.handle.net/11375/13396


McMaster University

15. Chatharaju, Madhuri. Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors.

Degree: MASc, 2011, McMaster University

Supercritical Water-cooled Reactor (SCWR) is a Generation-IV nuclear reactor design that operates on a direct energy conversion cycle above the thermodynamic critical point of… (more)

Subjects/Keywords: Supercritical water cooled reactors; LOCA; Critical flow; Thermal hydraulics; Safety Analysis; CFD; STAR-CCM+; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Chatharaju, M. (2011). Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11115

Chicago Manual of Style (16th Edition):

Chatharaju, Madhuri. “Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors.” 2011. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/11115.

MLA Handbook (7th Edition):

Chatharaju, Madhuri. “Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors.” 2011. Web. 15 Feb 2019.

Vancouver:

Chatharaju M. Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/11115.

Council of Science Editors:

Chatharaju M. Computational Study of Critical Flow Discharge in Supercritical Water Cooled Reactors. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11115

16. Zhou, Feng. CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes.

Degree: MASc, 2014, McMaster University

 Due to the recent advancement in computer capability, numerical modelling starts to play an important role in making predictions and improving the understanding of physics… (more)

Subjects/Keywords: SCWR; Heat Transfer; CFD; Deterioration Mechanism; Turbulence; Buoyancy

McMaster University - Engineering Physics 1. Introduction Nuclear energy has increasingly been… …With such a high reactor outlet 1 M.A. Sc. Thesis – F. Zhou; McMaster University… …Sc. Thesis – F. Zhou; McMaster University - Engineering Physics Figure 2 Operating… …Zhou; McMaster University - Engineering Physics The strong variations of thermal-physical… …Sc. Thesis – F. Zhou; McMaster University - Engineering Physics experimental approach due… 

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APA (6th Edition):

Zhou, F. (2014). CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/16243

Chicago Manual of Style (16th Edition):

Zhou, Feng. “CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes.” 2014. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/16243.

MLA Handbook (7th Edition):

Zhou, Feng. “CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes.” 2014. Web. 15 Feb 2019.

Vancouver:

Zhou F. CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes. [Internet] [Masters thesis]. McMaster University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/16243.

Council of Science Editors:

Zhou F. CFD Study of Convective Heat Transfer to Carbon Dioxide and Water at Supercritical Pressures in Vertical Circular Pipes. [Masters Thesis]. McMaster University; 2014. Available from: http://hdl.handle.net/11375/16243

17. McClure, Darryl. A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle.

Degree: MASc, 2014, McMaster University

The research and development effort for the next generation of nuclear power stations is being coordinated by the Generation IV International Forum (GIF). The supercritical… (more)

Subjects/Keywords: CFD; Heat Transfer; Fluid mechanics; STAR-CCM+; Turbulence Modelling; SCWR

…McClure M.A.Sc. Thesis Chapter 1 Introduction McMaster University Engineering Physics Chapter… …Supercritical Water Reactor 1 D. McClure M.A.Sc. Thesis Chapter 1 Introduction McMaster University… …D. McClure M.A.Sc. Thesis 1.2 Chapter 1 Introduction McMaster University Engineering… …2.1. 3 D. McClure M.A.Sc. Thesis Chapter 1 Introduction McMaster University Engineering… …others. This will 4 D. McClure M.A.Sc. Thesis Chapter 1 Introduction McMaster University… 

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APA (6th Edition):

McClure, D. (2014). A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/15392

Chicago Manual of Style (16th Edition):

McClure, Darryl. “A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle.” 2014. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/15392.

MLA Handbook (7th Edition):

McClure, Darryl. “A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle.” 2014. Web. 15 Feb 2019.

Vancouver:

McClure D. A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle. [Internet] [Masters thesis]. McMaster University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/15392.

Council of Science Editors:

McClure D. A Computational Benchmark Study of Forced Convective Heat Transfer to Water at Supercritical Pressure Flowing Within a 7 Rod Bundle. [Masters Thesis]. McMaster University; 2014. Available from: http://hdl.handle.net/11375/15392

18. Jacinto, Edilson Nogueira. Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions.

Degree: MSc, 2014, McMaster University

A considerable amount of effort is expended to better characterize and avoid the critical heat flux (CHF) phenomena in nuclear reactor systems. Most fuel assemblies… (more)

…Thesis Chapter 1 Introduction McMaster University Engineering Physics 1. Introduction A… …Thesis Chapter 1 Introduction McMaster University Engineering Physics analysis computer… …Jacinto M.A.Sc. Thesis Chapter 1 Introduction McMaster University Engineering Physics occurs… …3 Edilson Jacinto M.A.Sc. Thesis Chapter 1 Introduction McMaster University… …Introduction McMaster University Engineering Physics mixing between sub-channel volumes. Both of… 

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APA (6th Edition):

Jacinto, E. N. (2014). Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/16536

Chicago Manual of Style (16th Edition):

Jacinto, Edilson Nogueira. “Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions.” 2014. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/16536.

MLA Handbook (7th Edition):

Jacinto, Edilson Nogueira. “Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions.” 2014. Web. 15 Feb 2019.

Vancouver:

Jacinto EN. Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions. [Internet] [Masters thesis]. McMaster University; 2014. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/16536.

Council of Science Editors:

Jacinto EN. Experimental Study of Single Phase Turbulent Pipe Flow with Variable Obstructions. [Masters Thesis]. McMaster University; 2014. Available from: http://hdl.handle.net/11375/16536

19. Scriven, Michael. Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel.

Degree: MASc, 2015, McMaster University

The Pressure Tube Super Critical Water Reactor (PT-SCWR) is a design with a light water coolant operating at 25 MPa above the thermodynamic critical pressure,… (more)

Subjects/Keywords: Nuclear Physics; PT-SCWR; Lattice Codes; Neutronics; Coolant Density Variation; Benchmark

…region in 1 M.A.Sc. Thesis: M.G.Scriven, Engineering Physics McMaster University CHAPTER 1… …M.G.Scriven, Engineering Physics McMaster University CHAPTER 1 Figure 1.1: PT-SCWR 78-Element fuel… …M.A.Sc. Thesis: M.G.Scriven, Engineering Physics McMaster University CHAPTER 1 Light water at… …McMaster University CHAPTER 1 Table 1.2: Isotopic composition of Pu driver fuel derived from… …Engineering Physics McMaster University CHAPTER 1 Figure 1.3: Coolant properties along length of… 

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APA (6th Edition):

Scriven, M. (2015). Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/16592

Chicago Manual of Style (16th Edition):

Scriven, Michael. “Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel.” 2015. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/16592.

MLA Handbook (7th Edition):

Scriven, Michael. “Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel.” 2015. Web. 15 Feb 2019.

Vancouver:

Scriven M. Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel. [Internet] [Masters thesis]. McMaster University; 2015. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/16592.

Council of Science Editors:

Scriven M. Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel. [Masters Thesis]. McMaster University; 2015. Available from: http://hdl.handle.net/11375/16592

20. Joyal, David A. Axisymmetric Jet Impingement onto a Heated Cylinder.

Degree: MASc, 2017, McMaster University

The prediction of the flows and temperatures in the moderator system of CANDU reactors is important in the safety evaluation during some potential transients. An… (more)

Subjects/Keywords: Thermahydraulics; Jet Impingement; Moderator; CFD

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APA (6th Edition):

Joyal, D. A. (2017). Axisymmetric Jet Impingement onto a Heated Cylinder. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/22183

Chicago Manual of Style (16th Edition):

Joyal, David A. “Axisymmetric Jet Impingement onto a Heated Cylinder.” 2017. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/22183.

MLA Handbook (7th Edition):

Joyal, David A. “Axisymmetric Jet Impingement onto a Heated Cylinder.” 2017. Web. 15 Feb 2019.

Vancouver:

Joyal DA. Axisymmetric Jet Impingement onto a Heated Cylinder. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/22183.

Council of Science Editors:

Joyal DA. Axisymmetric Jet Impingement onto a Heated Cylinder. [Masters Thesis]. McMaster University; 2017. Available from: http://hdl.handle.net/11375/22183


McMaster University

21. Muhana, Ala. Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers.

Degree: MASc, 2009, McMaster University

Canada Deuterium Uranium, CANDU, nuclear reactors use forced convection cooling to remove heat from the nuclear fuel and transport it to the power production… (more)

Subjects/Keywords: Engineering Physics; Engineering Physics

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

APA (6th Edition):

Muhana, A. (2009). Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/9494

Chicago Manual of Style (16th Edition):

Muhana, Ala. “Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers.” 2009. Masters Thesis, McMaster University. Accessed February 15, 2019. http://hdl.handle.net/11375/9494.

MLA Handbook (7th Edition):

Muhana, Ala. “Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers.” 2009. Web. 15 Feb 2019.

Vancouver:

Muhana A. Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers. [Internet] [Masters thesis]. McMaster University; 2009. [cited 2019 Feb 15]. Available from: http://hdl.handle.net/11375/9494.

Council of Science Editors:

Muhana A. Validation of Computational Fluid Dynamic Tools for Single-Phase Flow Distribution in CANDU Headers. [Masters Thesis]. McMaster University; 2009. Available from: http://hdl.handle.net/11375/9494

.