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You searched for subject:(CANDU). Showing records 1 – 30 of 58 total matches.

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McMaster University

1. Strack, James Michael Vincent. A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model.

Degree: PhD, 2019, McMaster University

 The prediction of the moderator temperature distribution in a CANDU reactor is important in establishing its ability to act as an emergency heat sink for… (more)

Subjects/Keywords: CANDU; moderator

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

APA (6th Edition):

Strack, J. M. V. (2019). A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/23863

Chicago Manual of Style (16th Edition):

Strack, James Michael Vincent. “A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model.” 2019. Doctoral Dissertation, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/23863.

MLA Handbook (7th Edition):

Strack, James Michael Vincent. “A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model.” 2019. Web. 26 May 2019.

Vancouver:

Strack JMV. A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model. [Internet] [Doctoral dissertation]. McMaster University; 2019. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/23863.

Council of Science Editors:

Strack JMV. A Study of the Thermal-Hydraulic Behaviour of the Bruce A CANDU Moderator Using a Small-Scale Model. [Doctoral Dissertation]. McMaster University; 2019. Available from: http://hdl.handle.net/11375/23863


University of Ontario Institute of Technology

2. Shukla, Shivam. Design and development of a robotic crawler for CANDU fuel channel inspection.

Degree: 2015, University of Ontario Institute of Technology

 For the design of a new robotic crawler drive unit for CANDU fuel channel inspection, a complete design and screening process was done in order… (more)

Subjects/Keywords: Robotic; Crawler; CANDU; Inspection; Design

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APA (6th Edition):

Shukla, S. (2015). Design and development of a robotic crawler for CANDU fuel channel inspection. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/574

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

Chicago Manual of Style (16th Edition):

Shukla, Shivam. “Design and development of a robotic crawler for CANDU fuel channel inspection.” 2015. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/574.

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

MLA Handbook (7th Edition):

Shukla, Shivam. “Design and development of a robotic crawler for CANDU fuel channel inspection.” 2015. Web. 26 May 2019.

Vancouver:

Shukla S. Design and development of a robotic crawler for CANDU fuel channel inspection. [Internet] [Thesis]. University of Ontario Institute of Technology; 2015. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/574.

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

Council of Science Editors:

Shukla S. Design and development of a robotic crawler for CANDU fuel channel inspection. [Thesis]. University of Ontario Institute of Technology; 2015. Available from: http://hdl.handle.net/10155/574

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


University of Ontario Institute of Technology

3. Farkas, Robert. Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.

Degree: 2014, University of Ontario Institute of Technology

 When the coolant is voided in a CANDU lattice, the net reactivity change is positive, due primarily to the fact that the coolant and moderator… (more)

Subjects/Keywords: CANDU; CVR; Moderator displacers

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APA (6th Edition):

Farkas, R. (2014). Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/444

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

Chicago Manual of Style (16th Edition):

Farkas, Robert. “Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.” 2014. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/444.

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

MLA Handbook (7th Edition):

Farkas, Robert. “Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.” 2014. Web. 26 May 2019.

Vancouver:

Farkas R. Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study. [Internet] [Thesis]. University of Ontario Institute of Technology; 2014. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/444.

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

Council of Science Editors:

Farkas R. Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study. [Thesis]. University of Ontario Institute of Technology; 2014. Available from: http://hdl.handle.net/10155/444

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


University of Ontario Institute of Technology

4. Manning, Mark. Localization of a robotic crawler for CANDU fuel channel inspection.

Degree: 2017, University of Ontario Institute of Technology

 This thesis discusses the design and development of a pipe crawling robot for the purpose of CANDU fuel channel inspection. The pipe crawling robot shall… (more)

Subjects/Keywords: Robotics; Localization; CANDU; Inspection

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APA (6th Edition):

Manning, M. (2017). Localization of a robotic crawler for CANDU fuel channel inspection. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/801

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

Chicago Manual of Style (16th Edition):

Manning, Mark. “Localization of a robotic crawler for CANDU fuel channel inspection.” 2017. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/801.

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

MLA Handbook (7th Edition):

Manning, Mark. “Localization of a robotic crawler for CANDU fuel channel inspection.” 2017. Web. 26 May 2019.

Vancouver:

Manning M. Localization of a robotic crawler for CANDU fuel channel inspection. [Internet] [Thesis]. University of Ontario Institute of Technology; 2017. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/801.

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

Council of Science Editors:

Manning M. Localization of a robotic crawler for CANDU fuel channel inspection. [Thesis]. University of Ontario Institute of Technology; 2017. Available from: http://hdl.handle.net/10155/801

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


University of Ontario Institute of Technology

5. Golesorkhi, Sourena. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.

Degree: 2015, University of Ontario Institute of Technology

 The thorium fuel cycle is a promising future option for an alternative to uranium. The pressure tube heavy water reactor (PT-HWR) has for decades been… (more)

Subjects/Keywords: Thorium; PT-HWR; Breeder reactor; SSET; CANDU

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APA (6th Edition):

Golesorkhi, S. (2015). An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/617

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

Chicago Manual of Style (16th Edition):

Golesorkhi, Sourena. “An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.” 2015. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/617.

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

MLA Handbook (7th Edition):

Golesorkhi, Sourena. “An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.” 2015. Web. 26 May 2019.

Vancouver:

Golesorkhi S. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. [Internet] [Thesis]. University of Ontario Institute of Technology; 2015. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/617.

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

Council of Science Editors:

Golesorkhi S. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. [Thesis]. University of Ontario Institute of Technology; 2015. Available from: http://hdl.handle.net/10155/617

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


University of Ontario Institute of Technology

6. Gilbert, Jordan. Simulation of in-core dose rates for an offline CANDU reactor.

Degree: 2016, University of Ontario Institute of Technology

 This thesis describes the development of a Monte Carlo simulation to predict the dose rates that will be encountered by a novel robotic inspection system… (more)

Subjects/Keywords: MCNP; CANDU; Fuel channel; Inspections; Dose

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APA (6th Edition):

Gilbert, J. (2016). Simulation of in-core dose rates for an offline CANDU reactor. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/642

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

Chicago Manual of Style (16th Edition):

Gilbert, Jordan. “Simulation of in-core dose rates for an offline CANDU reactor.” 2016. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/642.

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

MLA Handbook (7th Edition):

Gilbert, Jordan. “Simulation of in-core dose rates for an offline CANDU reactor.” 2016. Web. 26 May 2019.

Vancouver:

Gilbert J. Simulation of in-core dose rates for an offline CANDU reactor. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/642.

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

Council of Science Editors:

Gilbert J. Simulation of in-core dose rates for an offline CANDU reactor. [Thesis]. University of Ontario Institute of Technology; 2016. Available from: http://hdl.handle.net/10155/642

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


University of Ontario Institute of Technology

7. Wijayaratne, Uditha. A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes.

Degree: 2018, University of Ontario Institute of Technology

 Wall thinning of carbon steel in CANDU reactor outlet feeder pipes due to Flow Accelerated Corrosion (FAC) is identified as one of the challenges for… (more)

Subjects/Keywords: CFD; Wall shear stress; CANDU; Numerical modelling

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APA (6th Edition):

Wijayaratne, U. (2018). A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/907

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

Chicago Manual of Style (16th Edition):

Wijayaratne, Uditha. “A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes.” 2018. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/907.

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

MLA Handbook (7th Edition):

Wijayaratne, Uditha. “A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes.” 2018. Web. 26 May 2019.

Vancouver:

Wijayaratne U. A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes. [Internet] [Thesis]. University of Ontario Institute of Technology; 2018. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/907.

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

Council of Science Editors:

Wijayaratne U. A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes. [Thesis]. University of Ontario Institute of Technology; 2018. Available from: http://hdl.handle.net/10155/907

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


Texas A&M University

8. Gowthahalli Chandregowda, Nandan. Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage.

Degree: 2012, Texas A&M University

 The Korea Hydro and Nuclear Power has built a new modular type of dry storage facility, known as MACSTOR KN-400 at Wolsong reactor site. The… (more)

Subjects/Keywords: MACSTOR KN-400; CANDU; Gamma; Neutron

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APA (6th Edition):

Gowthahalli Chandregowda, N. (2012). Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697

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

Chicago Manual of Style (16th Edition):

Gowthahalli Chandregowda, Nandan. “Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage.” 2012. Thesis, Texas A&M University. Accessed May 26, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697.

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

MLA Handbook (7th Edition):

Gowthahalli Chandregowda, Nandan. “Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage.” 2012. Web. 26 May 2019.

Vancouver:

Gowthahalli Chandregowda N. Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697.

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

Council of Science Editors:

Gowthahalli Chandregowda N. Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11697

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


University of Toronto

9. Karchev, Zheko. A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels.

Degree: 2009, University of Toronto

The present work focuses on the study of two-phase flow behavior called “Intermittent Buoyancy Induced Flow” (IBIF) resulting from the loss of coolant circulation in… (more)

Subjects/Keywords: CANDU Reactor, two-phase flow; 0542

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APA (6th Edition):

Karchev, Z. (2009). A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels. (Masters Thesis). University of Toronto. Retrieved from http://hdl.handle.net/1807/18784

Chicago Manual of Style (16th Edition):

Karchev, Zheko. “A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels.” 2009. Masters Thesis, University of Toronto. Accessed May 26, 2019. http://hdl.handle.net/1807/18784.

MLA Handbook (7th Edition):

Karchev, Zheko. “A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels.” 2009. Web. 26 May 2019.

Vancouver:

Karchev Z. A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels. [Internet] [Masters thesis]. University of Toronto; 2009. [cited 2019 May 26]. Available from: http://hdl.handle.net/1807/18784.

Council of Science Editors:

Karchev Z. A Study of Intermittent Buoyancy Induced Flow Phenomena in CANDU Fuel Channels. [Masters Thesis]. University of Toronto; 2009. Available from: http://hdl.handle.net/1807/18784


McMaster University

10. 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 May 26, 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. 26 May 2019.

Vancouver:

Hollingshead CW. CHARACTERIZATION OF THE INLET FLOW CONDITIONS FOR THE MODERATOR TEST FACILITY. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 May 26]. 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

11. 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 May 26, 2019. http://hdl.handle.net/11375/23471.

MLA Handbook (7th Edition):

Zhou, Feng. “Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors.” 2018. Web. 26 May 2019.

Vancouver:

Zhou F. Mechanistic Modeling of Station Blackout Accidents for CANDU Reactors. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 May 26]. 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

12. Matthews, Christopher. Analysis of the antineutrino rate during CANDU reactor startup.

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

 Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to… (more)

Subjects/Keywords: CANDU; Antineutrinos

…59 A CANDU Technical Data… …7 1.4: Fission rates for several isotopes in a typical CANDU bundle ...................9… …11 1.7: 37-pin CANDU fuel bundle… …16 1.8: Typical refueling operation for a CANDU reactor… …18 1.10: Location of depleted bundles in fresh CANDU core ...............................19… 

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APA (6th Edition):

Matthews, C. (2012). Analysis of the antineutrino rate during CANDU reactor startup. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/27973

Chicago Manual of Style (16th Edition):

Matthews, Christopher. “Analysis of the antineutrino rate during CANDU reactor startup.” 2012. Masters Thesis, Oregon State University. Accessed May 26, 2019. http://hdl.handle.net/1957/27973.

MLA Handbook (7th Edition):

Matthews, Christopher. “Analysis of the antineutrino rate during CANDU reactor startup.” 2012. Web. 26 May 2019.

Vancouver:

Matthews C. Analysis of the antineutrino rate during CANDU reactor startup. [Internet] [Masters thesis]. Oregon State University; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/1957/27973.

Council of Science Editors:

Matthews C. Analysis of the antineutrino rate during CANDU reactor startup. [Masters Thesis]. Oregon State University; 2012. Available from: http://hdl.handle.net/1957/27973


McMaster University

13. Yee, Shaun Sia Ho. Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor.

Degree: MASc, 2015, McMaster University

Fuels comprised of the element thorium have become increasingly popular with researchers and the public as the next generation fuel due to its ability to… (more)

Subjects/Keywords: Thorium; CANDU-6; CANDU; Multi-cell; DRAGON; DONJON; U-233; Th-232; Breeding

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APA (6th Edition):

Yee, S. S. H. (2015). Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/18187

Chicago Manual of Style (16th Edition):

Yee, Shaun Sia Ho. “Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor.” 2015. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/18187.

MLA Handbook (7th Edition):

Yee, Shaun Sia Ho. “Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor.” 2015. Web. 26 May 2019.

Vancouver:

Yee SSH. Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor. [Internet] [Masters thesis]. McMaster University; 2015. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/18187.

Council of Science Editors:

Yee SSH. Modelling Pure Thorium Bundle Implementation in the CANDU-6 Reactor. [Masters Thesis]. McMaster University; 2015. Available from: http://hdl.handle.net/11375/18187


University of Ontario Institute of Technology

14. Patel, Amin. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.

Degree: 2010, University of Ontario Institute of Technology

 Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several… (more)

Subjects/Keywords: Applied reactor physics; Transport theory; Diffusion theory; CANDU; Nuclear reactor

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APA (6th Edition):

Patel, A. (2010). Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/87

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

Chicago Manual of Style (16th Edition):

Patel, Amin. “Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.” 2010. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/87.

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

MLA Handbook (7th Edition):

Patel, Amin. “Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices.” 2010. Web. 26 May 2019.

Vancouver:

Patel A. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. [Internet] [Thesis]. University of Ontario Institute of Technology; 2010. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/87.

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

Council of Science Editors:

Patel A. Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices. [Thesis]. University of Ontario Institute of Technology; 2010. Available from: http://hdl.handle.net/10155/87

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


University of Ontario Institute of Technology

15. Lee, Andrew. Petri net modeling of fault analysis for probabilistic risk assessment.

Degree: 2013, University of Ontario Institute of Technology

 Fault trees and event trees have been widely accepted as the modeling strategy to perform Probabilistic Risk Assessment (PRA). However, there are several limitations associated… (more)

Subjects/Keywords: Petri net; Fault analysis; Coherent; Non-Coherent; CANDU

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APA (6th Edition):

Lee, A. (2013). Petri net modeling of fault analysis for probabilistic risk assessment. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/334

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

Chicago Manual of Style (16th Edition):

Lee, Andrew. “Petri net modeling of fault analysis for probabilistic risk assessment.” 2013. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/334.

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

MLA Handbook (7th Edition):

Lee, Andrew. “Petri net modeling of fault analysis for probabilistic risk assessment.” 2013. Web. 26 May 2019.

Vancouver:

Lee A. Petri net modeling of fault analysis for probabilistic risk assessment. [Internet] [Thesis]. University of Ontario Institute of Technology; 2013. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/334.

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

Council of Science Editors:

Lee A. Petri net modeling of fault analysis for probabilistic risk assessment. [Thesis]. University of Ontario Institute of Technology; 2013. Available from: http://hdl.handle.net/10155/334

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


University of Ontario Institute of Technology

16. Haroon, Jawad. Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.

Degree: 2014, University of Ontario Institute of Technology

 In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle… (more)

Subjects/Keywords: Medical isotopes; CANDU; Molybdenum-99; Six-day curies; Linear heat rating

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APA (6th Edition):

Haroon, J. (2014). Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/455

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

Chicago Manual of Style (16th Edition):

Haroon, Jawad. “Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.” 2014. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/455.

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

MLA Handbook (7th Edition):

Haroon, Jawad. “Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.” 2014. Web. 26 May 2019.

Vancouver:

Haroon J. Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors. [Internet] [Thesis]. University of Ontario Institute of Technology; 2014. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/455.

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

Council of Science Editors:

Haroon J. Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors. [Thesis]. University of Ontario Institute of Technology; 2014. Available from: http://hdl.handle.net/10155/455

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


University of Ontario Institute of Technology

17. Carisse, Katarzyna. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.

Degree: 2014, University of Ontario Institute of Technology

 The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the… (more)

Subjects/Keywords: Applied reactor physics; Advanced homogenization; CANDU; PT-SCWR

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APA (6th Edition):

Carisse, K. (2014). Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/458

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

Chicago Manual of Style (16th Edition):

Carisse, Katarzyna. “Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.” 2014. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/458.

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

MLA Handbook (7th Edition):

Carisse, Katarzyna. “Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.” 2014. Web. 26 May 2019.

Vancouver:

Carisse K. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. [Internet] [Thesis]. University of Ontario Institute of Technology; 2014. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/458.

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

Council of Science Editors:

Carisse K. Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. [Thesis]. University of Ontario Institute of Technology; 2014. Available from: http://hdl.handle.net/10155/458

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


Ryerson University

18. Villero, David. Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels.

Degree: 2015, Ryerson University

 A combined finite element-Ritz method is developed to effectively model the 3D lowfrequency acoustics in CANDU fuel sub-channels. The complex acoustic behavior of CANDU fuel… (more)

Subjects/Keywords: Sound  – Measurement; CANDU reactors; Vibration tests; Vibration  – Measurement; Acoustics in engineering

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APA (6th Edition):

Villero, D. (2015). Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels. (Thesis). Ryerson University. Retrieved from https://digital.library.ryerson.ca/islandora/object/RULA%3A4223

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

Chicago Manual of Style (16th Edition):

Villero, David. “Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels.” 2015. Thesis, Ryerson University. Accessed May 26, 2019. https://digital.library.ryerson.ca/islandora/object/RULA%3A4223.

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

MLA Handbook (7th Edition):

Villero, David. “Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels.” 2015. Web. 26 May 2019.

Vancouver:

Villero D. Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels. [Internet] [Thesis]. Ryerson University; 2015. [cited 2019 May 26]. Available from: https://digital.library.ryerson.ca/islandora/object/RULA%3A4223.

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

Council of Science Editors:

Villero D. Development of a Combined-Ritz Method for Modeling 3D Acoustics in Candu Fuel Sub-Channels. [Thesis]. Ryerson University; 2015. Available from: https://digital.library.ryerson.ca/islandora/object/RULA%3A4223

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

19. Chauhan, Aseem Kirtiman 1991-. MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750.

Degree: 2016, University of Saskatchewan

 Nickel alloys have found ever increasing use in the nuclear sector in recent times. Inconel X750 and other nickel-based alloys are used in the construction… (more)

Subjects/Keywords: Nickel alloys; CANDU reactor

…for Inconel X750 and Pure Ni 54 viii LIST OF FIGURES Figure 2.1: CANDU reactor schematic… …4 Figure 2.2: CANDU Fuel Channel Arrangement 5 Figure 2.3: Inconel X750 spacers (… …garter springs) in a fuel channel of a CANDU reactor 6 Figure 2.4: Inconel X750 spacers… …X750 (at maximum concentration of Ni) in the core of the CANDU reactor 11 Figure… …concentration of Ni) in the core of the CANDU reactor 12 Figure 2.8: Calculated helium… 

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APA (6th Edition):

Chauhan, A. K. 1. (2016). MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750. (Thesis). University of Saskatchewan. Retrieved from http://hdl.handle.net/10388/7361

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

Chicago Manual of Style (16th Edition):

Chauhan, Aseem Kirtiman 1991-. “MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750.” 2016. Thesis, University of Saskatchewan. Accessed May 26, 2019. http://hdl.handle.net/10388/7361.

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

MLA Handbook (7th Edition):

Chauhan, Aseem Kirtiman 1991-. “MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750.” 2016. Web. 26 May 2019.

Vancouver:

Chauhan AK1. MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750. [Internet] [Thesis]. University of Saskatchewan; 2016. [cited 2019 May 26]. Available from: http://hdl.handle.net/10388/7361.

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

Council of Science Editors:

Chauhan AK1. MICROSTRUCTURAL ANALYSIS OF HELIUM DISTRIBUTION IN NICKEL AND INCONEL X750. [Thesis]. University of Saskatchewan; 2016. Available from: http://hdl.handle.net/10388/7361

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


McMaster University

20. Dion, Alexander. A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating.

Degree: MASc, 2016, McMaster University

Under normal operating conditions a CANDU reactor pressure tube (PT) is insulated from its outer calandria tube (CT) by a CO2 gas annulus. If the… (more)

Subjects/Keywords: Thermal Hydraulics; CANDU; Fuel Channel Failure; Film Boiling

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APA (6th Edition):

Dion, A. (2016). A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/20647

Chicago Manual of Style (16th Edition):

Dion, Alexander. “A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating.” 2016. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/20647.

MLA Handbook (7th Edition):

Dion, Alexander. “A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating.” 2016. Web. 26 May 2019.

Vancouver:

Dion A. A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating. [Internet] [Masters thesis]. McMaster University; 2016. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/20647.

Council of Science Editors:

Dion A. A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating. [Masters Thesis]. McMaster University; 2016. Available from: http://hdl.handle.net/11375/20647


University of Ottawa

21. Don, Armel. Structure of Turbulent Flow in a Rod Bundle .

Degree: 2016, University of Ottawa

 The structure of turbulence in the subchannels of a large-scale 60 degree section of a CANDU 37-rod bundle was studied at Reynolds numbers equal to… (more)

Subjects/Keywords: CANDU; coherent vortices; thermalhydraulics; rod bundle; vortex street; subchannel

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APA (6th Edition):

Don, A. (2016). Structure of Turbulent Flow in a Rod Bundle . (Thesis). University of Ottawa. Retrieved from http://hdl.handle.net/10393/34154

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

Chicago Manual of Style (16th Edition):

Don, Armel. “Structure of Turbulent Flow in a Rod Bundle .” 2016. Thesis, University of Ottawa. Accessed May 26, 2019. http://hdl.handle.net/10393/34154.

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

MLA Handbook (7th Edition):

Don, Armel. “Structure of Turbulent Flow in a Rod Bundle .” 2016. Web. 26 May 2019.

Vancouver:

Don A. Structure of Turbulent Flow in a Rod Bundle . [Internet] [Thesis]. University of Ottawa; 2016. [cited 2019 May 26]. Available from: http://hdl.handle.net/10393/34154.

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

Council of Science Editors:

Don A. Structure of Turbulent Flow in a Rod Bundle . [Thesis]. University of Ottawa; 2016. Available from: http://hdl.handle.net/10393/34154

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


McMaster University

22. Trudell, David A. A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor.

Degree: MASc, 2012, McMaster University

The CANDU-900 reactor design is an improvement on the current CANDU-6 reactor in the areas of economics, safety of operation and fuel cycle flexibility.… (more)

Subjects/Keywords: CANDU; Load following; TRUMOX; Controllability; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Trudell, D. A. (2012). A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/12584

Chicago Manual of Style (16th Edition):

Trudell, David A. “A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor.” 2012. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/12584.

MLA Handbook (7th Edition):

Trudell, David A. “A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor.” 2012. Web. 26 May 2019.

Vancouver:

Trudell DA. A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor. [Internet] [Masters thesis]. McMaster University; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/12584.

Council of Science Editors:

Trudell DA. A Controllability Study of TRUMOX Fuel for Load Following Operation in a CANDU-900 Reactor. [Masters Thesis]. McMaster University; 2012. Available from: http://hdl.handle.net/11375/12584

23. Bui, Van Minh. La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors.

Degree: Docteur es, Constituants élémentaires et physique théorique, 2012, Nantes, Ecole des Mines

Aujourd’hui, l’énergie nucléaire représente une partie non-négligeable du marché énergétique mondial, très probablement vouée à croître dans les prochaines décennies. Les réacteurs du futur devront… (more)

Subjects/Keywords: Antineutrinos; Non-prolifération; Puissance résiduelle; Réacteur nucléaire; CANDU; Osiris; Nucifer; Décroissance bêta; TAGS; Effet Pandémonium; Antineutrinos; Non-proliferation; Decay heat; Nuclear reactor; CANDU; Osiris; Nucifer; Beta decay; TAGS; Pandemonium effect

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APA (6th Edition):

Bui, V. M. (2012). La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors. (Doctoral Dissertation). Nantes, Ecole des Mines. Retrieved from http://www.theses.fr/2012EMNA0004

Chicago Manual of Style (16th Edition):

Bui, Van Minh. “La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors.” 2012. Doctoral Dissertation, Nantes, Ecole des Mines. Accessed May 26, 2019. http://www.theses.fr/2012EMNA0004.

MLA Handbook (7th Edition):

Bui, Van Minh. “La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors.” 2012. Web. 26 May 2019.

Vancouver:

Bui VM. La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors. [Internet] [Doctoral dissertation]. Nantes, Ecole des Mines; 2012. [cited 2019 May 26]. Available from: http://www.theses.fr/2012EMNA0004.

Council of Science Editors:

Bui VM. La décroissance bêta des produits de fission pour la non-prolifération et la puissance résiduelle des réacteurs nucléaires : Beta decay of fission products for the non-proliferation and decay heat of nuclear reactors. [Doctoral Dissertation]. Nantes, Ecole des Mines; 2012. Available from: http://www.theses.fr/2012EMNA0004


University of Ontario Institute of Technology

24. Ahmed, Fayyaz. Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model.

Degree: 2011, University of Ontario Institute of Technology

 Industrial dynamical, Networked Control Systems (NCSs) are controlled over a communication network. We study a continuous-time CANada Deuterium Uranium-Super Critical Water Reactor (CANDU-SCWR) hydrogen plant… (more)

Subjects/Keywords: CANDU SCWR hydrogen co-generation model; Communication delays; Queuing delays; Scheduling delays

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APA (6th Edition):

Ahmed, F. (2011). Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/163

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

Chicago Manual of Style (16th Edition):

Ahmed, Fayyaz. “Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model.” 2011. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/163.

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

MLA Handbook (7th Edition):

Ahmed, Fayyaz. “Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model.” 2011. Web. 26 May 2019.

Vancouver:

Ahmed F. Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model. [Internet] [Thesis]. University of Ontario Institute of Technology; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/163.

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

Council of Science Editors:

Ahmed F. Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model. [Thesis]. University of Ontario Institute of Technology; 2011. Available from: http://hdl.handle.net/10155/163

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


University of Ontario Institute of Technology

25. Ahmad, Mohammad Mateen. Transmutation rates in the annulus gas of pressure tube water reactors.

Degree: 2011, University of Ontario Institute of Technology

CANDU (CANada Deuterium Uranium) reactor utilizes Pressure Tube (PT) fuel channel design and heavy water as a coolant. Fuel channel annulus gas acts as an… (more)

Subjects/Keywords: Annulus gas; CANDU; Fuel channel; MCNP; Neutron flux; Pressure tube reactor; Supercritical water reactor; Transmutation

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APA (6th Edition):

Ahmad, M. M. (2011). Transmutation rates in the annulus gas of pressure tube water reactors. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/182

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

Chicago Manual of Style (16th Edition):

Ahmad, Mohammad Mateen. “Transmutation rates in the annulus gas of pressure tube water reactors.” 2011. Thesis, University of Ontario Institute of Technology. Accessed May 26, 2019. http://hdl.handle.net/10155/182.

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

MLA Handbook (7th Edition):

Ahmad, Mohammad Mateen. “Transmutation rates in the annulus gas of pressure tube water reactors.” 2011. Web. 26 May 2019.

Vancouver:

Ahmad MM. Transmutation rates in the annulus gas of pressure tube water reactors. [Internet] [Thesis]. University of Ontario Institute of Technology; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/10155/182.

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

Council of Science Editors:

Ahmad MM. Transmutation rates in the annulus gas of pressure tube water reactors. [Thesis]. University of Ontario Institute of Technology; 2011. Available from: http://hdl.handle.net/10155/182

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


McMaster University

26. 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 May 26, 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. 26 May 2019.

Vancouver:

Younan S. Comparative study of accident-tolerant fuel for a CANDU lattice. [Internet] [Masters thesis]. McMaster University; 2017. [cited 2019 May 26]. 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

27. Gordon, Charles W. The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A).

Degree: MEngr, 1975, McMaster University

The optimal placement of shutdown systems in power reactors is investigated, in particular, the placement of mechanical and liquid shutoff rods. Two CANDU reactor… (more)

Subjects/Keywords: CANDU; optimal; power reactors; rods; reactivity

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APA (6th Edition):

Gordon, C. W. (1975). The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A). (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/18017

Chicago Manual of Style (16th Edition):

Gordon, Charles W. “The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A).” 1975. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/18017.

MLA Handbook (7th Edition):

Gordon, Charles W. “The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A).” 1975. Web. 26 May 2019.

Vancouver:

Gordon CW. The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A). [Internet] [Masters thesis]. McMaster University; 1975. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/18017.

Council of Science Editors:

Gordon CW. The Optimal Placement of Shutoff Rods in CANDU Nuclear Reactors (Part A). [Masters Thesis]. McMaster University; 1975. Available from: http://hdl.handle.net/11375/18017


McMaster University

28. Friedlander, Yonni. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.

Degree: MASc, 2011, McMaster University

A study was conducted to scope the relative merits of various thorium fuel cycles in CANDU reactors. It was determined that, due to the… (more)

Subjects/Keywords: Nuclear; Advanced Fuel Cycles; Thorium; CANDU; Nuclear resources; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Friedlander, Y. (2011). A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/11283

Chicago Manual of Style (16th Edition):

Friedlander, Yonni. “A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.” 2011. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/11283.

MLA Handbook (7th Edition):

Friedlander, Yonni. “A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS.” 2011. Web. 26 May 2019.

Vancouver:

Friedlander Y. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. [Internet] [Masters thesis]. McMaster University; 2011. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/11283.

Council of Science Editors:

Friedlander Y. A SCOPING STUDY OF ADVANCED THORIUM FUEL CYCLES FOR CANDU REACTORS. [Masters Thesis]. McMaster University; 2011. Available from: http://hdl.handle.net/11375/11283


McMaster University

29. Morreale, Andrew C. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.

Degree: PhD, 2012, McMaster University

The reprocessing of spent fuel is a key component in reducing the end waste from nuclear power plant operations and creating a sustainable closed… (more)

Subjects/Keywords: CANDU; Actinide Burning; Nuclear Safety Analysis; Mixed Oxide Fuel; Nuclear Engineering; Nuclear Engineering

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APA (6th Edition):

Morreale, A. C. (2012). Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/12784

Chicago Manual of Style (16th Edition):

Morreale, Andrew C. “Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.” 2012. Doctoral Dissertation, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/12784.

MLA Handbook (7th Edition):

Morreale, Andrew C. “Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor.” 2012. Web. 26 May 2019.

Vancouver:

Morreale AC. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. [Internet] [Doctoral dissertation]. McMaster University; 2012. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/12784.

Council of Science Editors:

Morreale AC. Analysis of Transuranic Mixed Oxide Fuel in a CANDU Nuclear Reactor. [Doctoral Dissertation]. McMaster University; 2012. Available from: http://hdl.handle.net/11375/12784


McMaster University

30. Langton, Stephanie E. Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis.

Degree: MASc, 2013, McMaster University

When simulating reactor physics experiments, uncertainties in nuclear data result in a bias between simulated and experimental values. For new reactor designs or for… (more)

Subjects/Keywords: (Th; Pu)O2; TSUNAMI; Sensitivity and Uncertainty; Nuclear; CANDU; Nuclear Engineering; Nuclear Engineering

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

APA (6th Edition):

Langton, S. E. (2013). Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/13027

Chicago Manual of Style (16th Edition):

Langton, Stephanie E. “Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis.” 2013. Masters Thesis, McMaster University. Accessed May 26, 2019. http://hdl.handle.net/11375/13027.

MLA Handbook (7th Edition):

Langton, Stephanie E. “Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis.” 2013. Web. 26 May 2019.

Vancouver:

Langton SE. Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis. [Internet] [Masters thesis]. McMaster University; 2013. [cited 2019 May 26]. Available from: http://hdl.handle.net/11375/13027.

Council of Science Editors:

Langton SE. Development of Applicable Benchmark Experiments for (Th,Pu)O2 Power Reactor Designs Using TSUNAMI Analysis. [Masters Thesis]. McMaster University; 2013. Available from: http://hdl.handle.net/11375/13027

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