Published: 2013-08-15

Articles

Critical Heat Flux and Heat Transfer Enhancement in Nuclear Fuel Bundles - A Review of the Past 50 Years

D.C. Groeneveld
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An integrated approach for Safer, Productive and Reliable PHWR fuel manufacturing at NFC

Nudurupati Saibaba
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Post-Irradiation Neutron Emissions From CANDU® Fuels and Their Nuclear Forensics Applications

Michel Couture
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The SLOWPOKE-2 Nuclear Reactor at The Royal Military College of Canada: Applications for the Canadian Armed Forces

Paul C. Hungler, M.T. Andrews, David G. Kelly, Kathy Nielsen
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Post-Irradiation Neutron Emissions From CANDU® Fuels And Their Nuclear Forensics Applications

Madison T. Sellers, David G. Kelly, Emily Corcoran
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Optimization of the Fuel Assembly for the Canadian Supercritical Water-cooled Reactor (SCWR)

Corey French, Paul K. Chan, H.W. Bonin
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FAST: A Combined NOC and Transient Fuel Model for CANDU® Fuel

Andrew Prudil, Brent J. Lewis, Paul K. Chan, J.J. Baschuk
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UO2 Fuel Oxidation

Fernando C. Iglesias, Brent J. Lewis
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Numerical Verification/Validation of the Theory of Coupled Reactors for Deuterium Critical Assembly, using MCNP5 and Serpent Codes

Mohamed Hussein, Brent J. Lewis, H.W. Bonin
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Development of a 3-D Finite Element Model to Examine Fuel Bundle Behaviour under Post-Dryout Heat Transfer Conditions

Cody Krasnaj, Paul K. Chan, Diane Wowk
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Feasibility Study of Modelling a CANDU Fuel Element Using a Multiphysics Object-Oriented Simulation Environment

Kyle Gamble, Paul K. Chan
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Beyond CANLUB-graphite: An Improved Alternative Coating Development

Kommy Farahani, G.A. Ferrier, Paul K. Chan, Emily Corcoran, Aniket Pant
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Heat Transfer Enhancement at Supercritical Pressures

Ahmad Eter, D.C. Groeneveld, Stavros Tavoularis, Nihan Onder
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Consideration of Subchannel Area of a 37-element Fuel to Enhance CHF

Joo Hwan Park, Jong Yeob Jung
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Fuel Behavior during Large Breaks in the Primary Heat Transport Circuit

Catalin Zalog, Emanoil-Relu Istrate
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Aging Effect on the Fuel Behaviors for CANDU® Fuel Safety Analysis

Jong Yeob Jung, Jun Ho Bae, Joo Hwan Park, Yong Man Song
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Assessing the Impact of the 37M Fuel Bundle Design on Fuel Safety Parameters

Khaled Shaheen, Mohamed Shawkat, Adrian Popescu, Hisham Hasanein, Hassan AlBasha
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Post-Irradiation Examination of the 37M Fuel Bundle at Chalk River Laboratories (AECL)

Jeffrey Armstrong, Todd Daniels, John Montin
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Optimization of Dissolution Process Parameters for Uranium Ore Concentrate Powders

M. Misra, A Reddy, S Tiwari, J Venkataswamy, D Setty, Saibaba Sheela, Nudurupati Saibaba
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Optimization of process parameters in precipitation for consistent quality UO2 powder production

S Tiwari, A Reddy, J Venkataswamy, M. Misra, D Setty, Saibaba Sheela, Nudurupati Saibaba
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Pellet Fabrication Development of Annular Pellets for Internally Cooled Annular Fuel

Andrew Bergeron, Holly Hamilton
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Application of Be-Free Zr-Based Amorphous Sputter Coatings as a Brazing Filler Metal in CANDU® Fuel Bundle Manufacture

Jung-Gu Lee, Min-Ku Lee, Chang-Kyu Rhee, Choon-Ho Park
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Metallurgical structure modification of UO2 pellet during Sintering

N Santra, T Sinha, A Singh, S. Sairam, Saibaba Sheela, Nudurupati Saibaba
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Design of a Molybdenum Based Oxygen Sensor to Assist in the Characterization of Defective CANDU Nuclear Fuels as a Function of Burnup

Robert A. Barry, Jennifer Scott, Emily Corcoran
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A Statistical Assessment Of CANDU® Fuel Manufacturing Parameters And Their Impact On In-Reactor Performance During Transient Conditions

Travis A. Cunning, Paul K. Chan, Mahesh Pandey, Aniket Pant
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Irradiation behaviour of Th-Pu and U-Pu MOX fuels

Prerna Mishra, V. Jathar, R.S. Shriwastaw, H.N. Singh, P.M. Satheesh, P.B. Kondejkar, G.K. Mallick, J. Singh, S. Anantharaman
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Fuel Deposits, Chemistry and CANDU® Reactor Operat

John G. Roberts
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Optimizing In-Bay Fuel Inspection Capability to Meet the Needs of Today's CANDU Fleet

Joe St-Pierre, Brendan Simons
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Regulatory Review Of The CANDU® Fuel Modification Program in Canada

Yujun Guo
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DME-221 Thoria Fuel: Fabrication, Irradiation Testing and Post-Irradiation Examination

Stavros Corbett, Holly Hamilton, Mark R. Floyd, Steve Livingstone, Noel F. Harrison
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Thoria Irradiation and Post-Irradiation Examination Experience at AECL

Steve Livingstone, Mark R. Floyd
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Fuel Performance Modeling for Proposed Th Based Canadian SCWR Fuel

John S. Bell, Paul K. Chan
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Analysis of Thorium/U-233 Lattices and Cores in a Breeder/Burner Heavy Water Reactor

Sourena Golesorkhi, Matthew H. Kaye
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Safety Assessment to Support NUE Fuel Full Core Implementation in CANDU® Reactors

Trish Laurie, H.Z. Fan, A Siddiqi, Daniel Rouben, Z.P Li, Catherine Cottrell
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Impact of the 37M Fuel Design on Reactor Physics Characteristics

Ricardo Perez, Patrick Ta
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Silicon Carbide TRIPLEX Materials for CANDU Fuel Cladding and Pressure Tubes

Herbert Feinroth, Gregory Markham, Matthew Ales, Michael Montgomery
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Results of Qualification Program Performed to Prepare 37M Fuel for Use in Darlington Nuclear Power Stations

Gordon I. Hadaller, Richard Van Lochem, Todd Daniels
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Improvements in In-Bay Irradiated Fuel Inspection Planning & Analysis at Bruce Power

David Millar, Ron Stark, Joe St-Pierre
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FLASHPOINT - – A Tool to Routinely Calculate the Heat Load in the Irradiated Fuel Bays

Eric Vyskocil, C. Morrison, E. Gifford, A. Inglot, K. Kozowski, M. Gocmanac, Y. Parlatan, H. Alabasha
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Examining the Viability of Ultrasonic Inspection of Discharged CANDU® Fuel Bundles

Thomas W. Krause, Willie H. Huang, Brent J. Lewis
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The effect of oxidized UO2 on iodine induced stress corrosion cracking of fuel sheathing

Aaron Quastel, Emily Corcoran, Brent J. Lewis
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Comparison between Zircaloy Oxidation in Steam and Air Surroundings

Mohamed Shawkat, Hisham Hasanein, Muhammad Ali, Yuksel Parlatan, Hassan AlBasha
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IAEA Programme to Support Development and Validation of Advanced Design and Safety Analysis Codes

Jong-Ho Choi
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Benchmarking a Fission-Product Release Computer Program Containing a Gibbs Energy Minimizer

Duncan H. Barber
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Analysis of Fuel End Temperature Peaking

Zhen Xu, Qing Jiang, Liping Lai, Masoud Shams
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Advanced CFD Simulations of Turbulent Flows Around Appendages in CANDU® Fuel Bundles

Farzin Abbasian, Gordon I. Hadaller, R.A. Fortman
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Modeling Coupled Bending, Axial, and Torsional Vibrations of a CANDU® Fuel Rod Subjected to Multiple Frictional Contact Constraints

Mohammad Fadaee, Shudong Yu
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Review of Zircaloy Oxidation Behaviour

Fernando C. Iglesias, Brent J. Lewis
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On-line fuel and control rod integrity surveillance in BWRs

Lembit Sihver, Irina Larsson, Helena Loner, Anette Grundin, Jan-Ola Helmersson, Guido Ledergerber
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Assessment of Causes for Degrading Fuel Performance at Darlington NGS

Jonathan Judah, Steve Goodchild
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