Sustainable Development
P. Lamarre (SNC Lavalin Nuclear)
Nuclear Recycle
W. Hannum (ex-USDOE)
Pressure Tube Reactors and the Sustainable Energy Future: The Ultra Development Path
R.B. Duffey (AECL)
Nuclear Regulation and Generation III Reactors
J.G. Waddington (CNSC)
Hydrogen Energy and Sustainability: Overview and the Role for Nuclear Energy
M.A. Rosen (UOIT)
Nuclear In The Oil Sands
P E. Isaacs (Alberta Energy Res. Inst)
B1 ADVANCED REACTORS - RÉACTEURS DE TYPE AVANCÉ
The ACR-1000 Fuel Design Verification Process
P. Reid, M. Tayal, M. Gacesa (AECL)
Molten Salt Reactors: A New Vision for a Generation IV Concept
D. LeBlanc (CU)
The Pebble Bed Modular Reactor (PBMR) as a Source of High Quality Process Heat for Sustainable Oil Sands Expansion
A. Morris, R. Kuhr (Shaw Stone & Webster)
Laser Peening Applications for Next Generation of Nuclear Power Facilities
J. Rankin, C. Truong, M. Walter, H.-L. Chen, L. Hackel (Metal Improvement Company)
BNA Pellet Material Properties Test Program in Support of ACR-1000 Fuel Design
J. Chang, Z. He, M. Gacesa, P. Reid (AECL)
Zirconia-Rare Earth Oxide Phase Stability Program in Support of ACR-1000 Fuel Design
J. Hood, F. Akbari, Z. He, P. Reid (AECL), E.C. Corcoran, B.J. Lewis, W.T. Thompson (CMRC/RMCC)
B2 PLANT & COMPONENTS I - CENTRALE ET COMPOSANTS I
The Latest Application of Hitachi-GE’s State-of-the-Art Construction Technology and Further Evolution Towards New Build NPP Projects
K. Akagi, K. Morita, R. Miyahara, K. Murayama (Hitachi-GE Nuclear Energy), C. Deir, S. Akahori (Hitachi Canada)
Hydraulic Nuts (Hydranuts) for Critical Bolted Joints
S. Greenwell (Curtiss-Wright Flow Control Nuclear)
An Analysis to Determine Industry’s Preferred Option for an Initial Generic Reliability Database for CANDU
D. Komljenovic (HQ), E. Chan (BP), S. Ganguli (OPG), J. Wu (AECL), R. Parmar (NSS)
Best Practices in Design & Delivery of a New Tritium Facility
I. Bonnett (GE Hitachi Nuclear Energy), A. Busigin (Special Separation Applications Inc.), A. Griffiths (GE Healthcare)
Use Of Soft-Metal Engineered Surfaces To Minimize Galling Of Carbon Steel Bolting Materials In Gasketed Joints At Elevated Temperatures
D.N. Hopkins, C.D. Harrington, S. Greenwell (Curtiss-Wright Flow Control Nuclear)
B3 PROCESS SYSTEMS I - SYSTÈMES FONCTIONNELS I
Generic And Profile Specific Feeder Stress Analysis
M. Li, M.L. Aggarwal (OPG)
Aqueous Solubility of Zirconia
S. Sunder, S. Wren (AECL)
Simulation of High-Temperature, Non-Congruent Phase Transitions in UO2+x
M.J. Welland, W.T. Thompson, B.J. Lewis (CMRC/RMCC)
Computed Phase Equilibria for Burnable Neutron Absorbing Materials for the Advanced CANDU Reactor Design
E.C. Corcoran, B.J. Lewis, W.T. Thompson (CMRC/RMCC)
New Shielding Materials with Advanced Gamma Absorption
S.G. Ermichev (All-Russian Research Institute of Experimental Physics ARRIEP), A.A. Maslov (Bochvar Institute of Inorganic Materials VNIINM), V.Z. Matveev, A.I. Morenko (ARRIEP), V.K. Orlov, A.G. Semenov, V.M. Sergeev (VNIINM), V.I. Shapovalov (ARRIEP), O.I. Yuferov, A.M. Visik (VNIINM)
B4 THERMALHYDRAULICS I - THERMOHYDRAULIQUE I
A Transient Neutronic-Thermalhydraulic Coupled Modelling Approach
M. Fassi Fehri, R. Chambon, A. Teyssedou (EPM)
Validation of Impinging Jet Models to be Used in CANDU Calandria Vessel CFD Simulations
Martin Bouquillon, Alberto Teyssedou, Eugenio Cuesta (EPM), Hong Huynh (HQ)
Experimental Investigation of Flow Obstacles Effect on Single Phase Heat Transfer
A. Tanase (UO), D.C. Groeneveld (AECL), H. Zahlan, S.C. Cheng (UO)
Fluid-Phase Transitions in Light Water and Heavy Water
R.L. Varty (Consultant)
Investigation of the Combined Effect of Appendages and Axial Power Profile on Post-Dryout Heat Transfer in Tubes
H. Zahlan (UO), D.C. Groeneveld, L.K.H. Leung (UO and AECL), A. Tanase, S.C. Cheng (UO)
Modeling the Quenching of a Calandria Tube Following a Critical Break LOCA in a CANDU Reactor
J.T. Jiang, J.C. Luxat (MacU)
B5 SAFETY & LICENSING - SÛRÉTE ET PERMIS
Modeling of Pickering NGS B Heat Transport System Seismic Boundary Leak Tightness Test
R. MacLeod, C. Lorencez (OPG)
Overview of Experimental Programs on Core Melt Progression and Fission Product Release Behaviour
B.J. Lewis (CMRC/RMCC), R. Dickson (AECL), F.C. Iglesias (Candesco)
How Safe is Safe Enough? The Canadian Answer
F. Boyd (Consultant, former AECB)
Fission Product Release Mechanisms: Research in Canada
F.C. Iglesias (Candesco), B.J. Lewis (CMRC/RMCC), A. Oliva (Candesco), P. Purdy (BP)
Using Statistical Inference for Decision Making in Best Estimate Analyses
P. Sermer, K. Weaver (NSS), F. Hoppe (MacU), C. Olive, D. Quach (NSS)
Determination of Realistic Margins to Fuel Heatup for Slow Loss of Regulation Accidents in a CANDU Reactor
D.R. Novog (MacU), P. Sermer, D. Quach (NSS), J.C. Luxat (MacU)
S1 MATERIALS AND FUEL - MATÉRIAUX ET COMBUSTIBLE
First Steps Toward a Mechanistic Model for Core Disassembly in a CANDU Reactor
R. Perez (MacU)
Pressure Tube-Calandria Tube Thermal Contact Conductance
A. Cziraky (MacU)
Intergranular Corrosion Mechanism of Alloy 400
W. Zhang (UT)
The Kinetics of Cathodic Oxygen Reduction on Thin Films on Ni-Cr-Mo (W) Alloys
X. Zhang, P. Jakupi, D. Zagidulin, J.J. Noël, D.W. Shoesmith (UWO)
Fuel Performance and Thermochemistry Modeling of CANDU Nuclear Fuel Progress in Developing a Self Standing Integrated Code
M.H.A. Piro (CMRC/RMCC)
A Simplified Oxidation Model for Defective Nuclear Fuel
K. Shaheen (CMRC/RMCC)
Modification of Fuel Bundles and Associated Optimization of Fuel Handling Equipment
P. Ponomaryov (Blue Water District Secondary School)
S2 HEALTH, MEDICAL AND NUCLEAR PHYSICS - SANTÉ, PHYSIQUE NUCLÉAIRE ET MÉDICALE
Modelling of Aircrew Radiation Exposure from Solar Particle Events
H. Al Anid, B.J. Lewis, L. Bennett (CMRC/RMCC)
Environmental Monitoring of Chinook Salmon
D. Morris, D. Boreham (MacU)
Diagnostic Imaging Procedures During Pregnancy: What are the Fetal Risks?
K. Taylor (MacU)
Effects of Low-Dose Gamma and Neutron Radiation on Genotoxicity and Cytotoxicity of Reticulocytes in a Mouse Model
N. Phan, N. McFarlane, J. Lemon, D. Boreham (MacU)
Effet d’une Vidange Stratifiée du Caloporteur sur la Réactivité et la Distribution du Flux Neutronique D'une Cellule CANDU-6
M. Massicotte (EPM)
Time Average CANDU Model with Fuel Reshuffling
K. Auyeung, S. Kelley, R. Godavarthi (UOIT)
B6 PRESIDENT'S PLENARY SESSION
Implementing Adaptive Phase Management for Canada's Used Nuclear Fuel
F. King (NWMO)
What's the Rest of the World Doing with its Spent Fuel?
T. Isaacs (Stanford University & LLNL)
What Canadians Say About Management of Used Nuclear Fuel
J.A. Facella (NWMO)
C1 HYDROGEN - L'HYDROGÈNE
Process Simulation of Nuclear-Based Thermochemical Hydrogen Production with a Copper-Chlorine Cycle
C.C. Chukwu, G.F. Naterer, M.A. Rosen (UOIT)
Safety Issues in Nuclear Hydrogen Production with the Very High Temperature Reactor (VHTR)
S. Baindur (Ottawa Policy Research Associates, Inc.)
Life Cycle Assessment of Nuclear-Based Hydrogen Production Using Thermochemical Water Decomposition: Extension of Previous Work and Future Needs
L.I. Lubis, I. Dincer, M.A. Rosen (UOIT)
Application of Multi-State Systems in Fault Tree Analysis of a Conceptual Thermochemical Hydrogen Plant
Y. Zhang, L. Lu, G.F. Naterer (UOIT)
Energy and Exergy Analyses of a Copper-Chlorine Thermochemical Water Decomposition Pilot Plant for Hydrogen Production
M.F. Orhan, I. Dincer, M.A. Rosen (UOIT)
Hydrodynamics of Cupric Chloride Hydrolysis in a Fluidized Bed for Nuclear Hydrogen Production
Y. Haseli, I. Dincer, G.F. Naterer (UOIT)
Thermochemical Process Heat Requirements of the Copper-Chlorine Cycle for Nuclear-Based Hydrogen Production
Z. Wang, K. Gabriel, G.F. Naterer (UOIT)
C2 PLANT & COMPONENTS II - CENTRALE ET COMPOSANTS II
An Introduction to a New IAEA Safety Guide: “Ageing Management for Nuclear Power Plants”
J. Pachner (Pachner Associates), T. Inagaki, K.S. Kang (IAEA)
Canadian Regulatory Oversight of Ageing Management for Nuclear Power Plants
K. Kirkhope, A. Blahoianu, G. Frappier (CNSC)
Plans to Adapt Point Lepreau Ageing Management to New Industry Guidelines
G. Greenlaw (NBP), T. Gendron (AECL), J. Slade, B. Rankin (NBP)
Current and Future Ultrasonic Inspection for CANDU SG Tubes
Z. Chen, K. Chan (Kinectrics), J. Huggins, T. Malkiewicz (OPG)
Stanpipes Moves to the Windows Environment
T. Stevens, B. Manning (OPG)
Ultrasonic Inspection of Tubes Without Rotation
A. Karpelson (Kinectrics)
Cable Condition Monitoring Using Non-Destructive and Non-Intrusive Fourier Transform Near Infrared (FT-NIR) Spectroscopy
H. Azizian (NIR Technologies), S. Benson (RCM Technologies Canada)
C3 HUMAN FACTORS - ERGONOMIC
New Laws of Practice for Learning and Error Correction
R.B. Duffey (AECL)
Human Factors in the Canadian Nuclear Industry: Future Needs
F. Harrison (CNSC)
Providing Operator Support During Monitoring for Unanticipated Events Through Ecological Interface Design
Nathan Lau, G.A. Jamieson (UT), G. Skraaning Jr. (OECD Halden Reactor Project), C.M. Burns (UW)
The Practical Aspects of Incorporating Hf Considerations into Design Changes at Nuclear Facilities – A Contractor’s Perspective
M. Hourihan, M. Remisz, P. Spagnolo (SNC-Lavalin Nuclear Inc.)
Utilization of Handheld Computing to Trend Improvements in Compliance
G. Galvin, J. Rasmussen, A. Haines (Industrial Audit)
Development of Public Acceptance and Market Success with Very Small Nuclear Power Reactors (VSR)
P. Lang (Independent)
C4 PHYSICS I - PHYSIQUE I
RFSP-IST Simulation of Fuel Transient During Refuelling of the ACR-1000 Reactor
J. Hu, I. Martchouk, R. Robinson (AECL)
Void Reactivity Studies for the Atucha-II PHWR Reactor - Preliminary Design of a Lower Void Reactivity Fuel
F. Khatchikian, J. Fink (Nucleoelectrica Argentina S.A.)
Modifications for Better Control of the First Radial Mode During Load-Cycling of the ACR-1000
G. Teneva (NSS), R. Robinson (Candesco)
Utilization of Simulated Annealing Algorithm in the ROP Detector Layout Optimisation
D. Kastanya, V. Caxaj (AECL)
Improvement and Qualification of WIMS Utilities
T. Liang, W. Shen, E. Varin, K. Ho (AECL)
Comparison of Bare-Lattice Calculations Using MCNP Against Measurements with CANFLEX-LEU in ZED-2
Y. Dweiri, B. Arsenault, M. Zeller (AECL)
Improved Linear Congruential Random Number Generators
H. Shen, P. Zhang, K. Wang (Tsinghua University)
C5 INSTRUMENTATION AND CONTROL - INSTRUMENTATION ET CONTRÔLE-COMMANDE
Fundamental OP&C Systems Structure in Nuclear Power Plants
K. Ishii, H. Harada, T. Yamamori, K. Igarashi (Hitachi), T. Arakida (Hitachi Canada)
Research on Visual Modeling and Simulation Method for Operational Flowsheets-Oriented CANDU Control Systems
Z. Cui (ANSL), R. Prime (NBP), K. Scott, M. McIntyre (ANSL)
Online Control Loop Tuning in Pickering Nuclear Generating Stations
K.X. Yu, S. Harrington (OPG)
Thermal Gradients Caused by the CANDU Moderator Circulation
V.K. Mohindra, M.A. Vartolomei (AECL), R. Scharfenberg (BP)
Modifications to Improve Reliability in Deaerator Level Control by Using Digital Technology
S. Harrington, K.X. Yu (OPG)
Reactor Building Indoor Wireless Network Channel Quality Estimation Using RSSI Measurement of Wireless Sensor Network
S. Merat (Wardrop)
S3 THERMALHYDRAULICS AND SAFETY - THERMOHYDRAULIQUE ET SÛRETÉ
Effects of Fluid Stream Impurities on Performance of a Supercritical CO2 Power Conversion System
D. Côté, A. Gagnon, D. Pucsek (CU)
Numerical Investigation of Turbulent Flow in a Twin Rectangular Sub-Channel Geometry
D. Home, M. Lightstone, M. Hamed (MacU)
Unsteady Reynolds Averaged Navier-Stokes (Urans) Modelling of Turbulent Flow in a Twin Rectangular Subchannel Geometry
G. Arvanitis, D. Home, M. Lightstone, M. Hamed (MacU)
Novel Design of a CHF Experimental Facility
B.A. Statham (MacU)
Validation of Fluent Software for Prediction of Flow Distribution and Pressure Gradients in a Multi-Branch Flow Header
A. Muhana, D. Novog (MacU)
An Approach to Modelling the Effects of a Small LOCA with a Loss of ECI Under Natural Circulation Conditions in a CANDU Reactor
D. Pohl (MacU)
Literature Investigation of Air/Steam Ingress through Small Cracks in Concrete Wall Under Pressure Differences
J.T. Jiang (MacU)
IEC 61508: Compatibility, Application and Requirements in Canadian Nuclear Industry
E. Zahedi (UT)
S4 CHEMISTRY - CHIMIE
Radiolysis of Water Containing Dissolved Nitrogen Species
P. Yakabuskie, J.M. Joseph, J.C. Wren (UWO)
Effect of Gamma Radiation on Steel Corrosion
K. Daub, X. Zhang, J.J. Noël, D. Shoesmith, J.C. Wren (UWO)
Film Breakdown Processes on Carbon Steel in the Presence of Large Anions
K. Yazdanfar, X. Zhang, D. Shoesmith, J.C. Wren (UWO)
Metal-Oxide Film Conversions Involving Large Anions
S. Pretty, X. Zhang, D. Shoesmith, J.C. Wren (UWO)
Electrochemical Impedance Spectroscopy Study of H2O2 Interaction with G-Feooh Single-Phase Films on the Gold Electrodes
D. Fu (UWO)
The Determination of Local Corrosion Kinetics Using Scanning Electrochemical Microscopy
H. He, Z. Qin, P.G. Keech, J.J. Noël, Z.F. Ding, D.W. Shoesmith (UWO)
Crevice Corrosion Damage Analysis on Ni-Cr-Mo Alloys Proposed for the Nuclear Waste Containers
P. Jakupi, D. Zagidulin, J.J. Noël, D. Shoesmith (UWO)
Surface Electrochemistry of UO2 in Dilute Acidic Hydrogen Peroxide Solutions
D. Hall, P.G. Keech, J.J. Noël, D.W. Shoesmith (UWO)
D1 HUMAN RESOURCES AND INFRASTRUCTURE - MEETING THE CHALLENGE / RESSOURCES HUMAINES ET INFRASTRUCTURE - FAIRE FACE AU DÉFI
COG's Contribution to the Industry
J. Froats (COG)
Tacit Knowledge Emergence
W. Garland (UNENE)
Human Resources - Meeting the Challenge: An Organization of CANDU Industries Perspective
M. Wash (OCI)
Women and the Nuclear Talent Pool: Myths and Perspectives on the Present and Future
S. Brissette (WIN Canada), B. Keenan (OPG)
E1 NUCLEAR TECHNOLOGIES SUPPORTING SUSTAINABLE DEVELOPMENT - TECHNOLOGIES NUCLÉAIRES AU SERVICE DU DÉVELOPPEMENT DURABLE
ACR-1000 Update
A. Alizadeh (AECL)
Global Deployment of the AP1000
B. Pearce (WEC)
EPR: The Path to Greatest Certainty
A. Laferrère (AREVA)
LUNCHEON TALK
NSC Future Directions
M. Binder (President, CNSC)
F1 ENVIRONMENT & WASTE MANAGEMENT - ENVIRONNEMENT ET GESTION DES DÉCHETS
Implementation of a Comprehensive Program to Deal with Canada’s Nuclear Legacy Liabilities: A Progress Report
J. Miller, S. Halpenny, S. Brooks, G. Dolinar, P.J. Ingham, S. Kenny, G Koroll, A. Melnyk (AECL), D. Metcalfe, M Blanchette (NRCan)
Commercial Implementation of an Innovative Multi-Stage Treatment System for Removal of Radiological and Chemical Contaminants to Near-Zero Levels
R. Davloor, W. Harper, D. Bastien, J. Rapley (BP)
Over-Packing of Spent Ion Exchange Resin Carbon Steel Liners at Ontario Power Generation’s Western Waste Management Facility
A. Husain (Kinectrics), D. Pearson, B. Sklar (Energy Solutions)
Environmental Assessment Planning for Nuclear New Build in Canada
D. Moffett, M. Mayhew (Golder Associates Ltd.), J. Scongack (BP)
Subduction for Permanent Disposal of Long-Lived Highly Radioactive Nuclear Waste
F.P. Ottensmeyer (UT)
Degradation and Bacterial Survival on Nuclear-Grade Ion Exchange Resins and Implications for Waste Management
T. Chiappetta, F. Caron, A. Omri (LU)
F2 PROCESS SYSTEMS II - SYSTÈMES FONCTIONNELS II
The Effect of Hydrazine on the Electrochemical Corrosion Potential of Steam Generator Tubing in the Presence of Oxygen
J.M. Smith, A.C. Lloyd (Kinectrics Inc)
Cracking of 304l Stainless Steel Observed Within CANDU Nuclear Power Plants Under Cyclic Moist Environments
R.G. Allen, G.I. Ogundele, A.C. Lloyd, D.K. Jain, A.K. Järvine (Kinectrics Inc.)
Evaluation of Crud Behavior in Primary Circuit of Integral Reactor by Multi-Region Model
B.S. Choi, W.-Y. Maeng, J.W. Yeon, J.H. Hong (KAERI), H.Y. Yang (KHNP), J.C. Wren (UWO)
A Probabilistic Approach to the Estimation of Lifetime Distribution of Alloy 800 SG Tubing
M.D. Pandey, S. Datla (UW), R.L. Tapping, Y.C. Lu (AECL)
Investigation into the Potential Release of Chloride from the Moderator Cover Gas Recombiner Catalyst
L. Stolberg, S. Suppiah, K. Kutchcoskie (AECL)
Study on the Dissolution of Uranium Dibutyl Phosphate Deposits
A.L. Rufus, V.S. Sathyaseelan, S. Velmurugan, S.V. Narasimhan (BARC)
F3 PHYSICS II - PHYSIQUE II
A keff Calculation Method by Monte Carlo
H. Shen, K. Wang (Tsinghua University, Beijing)
Modelling of Liquid Injection Shutdown System (LISS) in ACR-1000
M. Boubcher, A. Colton, J.V. Donnelly (AECL)
Comparison of Simulated Radioiodine Ratios with Measured Values for Three CANDU Stations
S. Mostofian, R. Khaloo, C.R. Boss (AECL)
Comparison of MCNP Calculations Against Measurements in Moderator Temperature Experiments with CANFLEX-LEU in ZED-2
D.G. Watts, F.P. Adams, M.B. Zeller, B.P. Bromley (AECL)
Simulation of Long-Term Fuelling Operations for the ACR-1000
R. Farkas, R. Robinson, A. Rehman, A. Buijs (AECL)
Design of a Guaranteed Shutdown State Using Solid Rods for the ACR-1000 Reactor
I. Hill, J.V. Donnelly, I. Martchouk, A. Buijs (AECL)
Methods for Characterizing Uncertainty Effects in Key Input Parameters Used in the 2-Dimensional Monte-Carlo Simulation of Dryout Power
D. Quach, P. Sermer (NSS), O. Nainer (BP), B. Phan (OPG)
F4 THERMALHYDRAULICS II - THERMOHYDRAULIQUE II
Heat Transfer Limitation during Rapid Depressurization
J.C. Luxat, D.R. Novog (MacU)
A Technical Basis for the Flux Corrected Local Conditions Critical Heat Flux Correlation
J.C. Luxat (MacU)
Application of the Simple Analytical Approach to Calculate Pressure Drop in Liquid Nitrogen Two Phase Flow over Large Distances Using Hoses
M.A. Aamir, D. Creates, P. Bekeris (OPG)
Mock-Up to Simulate Pipe Freezing in Shutdown Cooling Rooms
M.A. Aamir, P. Bekeris, D. Creates (OPG)
Multi-Objective Optimization of Thermodynamic Power Cycles Using an Evolutionary Algorithm
W. Hounkonnou, J. Dipama (EPM), F. Aubé (CANMET), A. Teyssedou (EPM)
Measurements of Turbulent Pressures of Flow in a Water-Conveying Pipe Containing a Simulation Fuel Bundle
F. Abbasian, J. Cao, S.D. Yu (RU)
F5 PLANT OPERATION - EXPLOITATION DE CENTRALE
Monitoring and Managing Component Fatigue in CANDU Stations
M. Yetisir (AECL), G.I. Stevens (SI Associates), S. Robertson (NBP), Y. Ding, G. Burton (AECL)
Reactivity Management in Control Room Operations
T. Primeau (BP), A. Dykeman (NBP)
Steam Generator Replacement at Bruce A: Approach, Results and Lessons Learned
W. Tomkiewicz, B. Savage, J. Smith (SNC-Lavalin Nuclear)
Evolution of Operations Culture
D. Gould (Cantech)
S5 INSTRUMENTATION AND CONTROL - INSTRUMENTATION ET CONTRÔLE-COMMANDE
Evaluation of Network Structures and Protocols for Nuclear-Specific Applications
P. Zahedi (Student)
Best Estimate Methods for Safety Analysis and Trip Assessment
A. Morreale (MacU)
Distributed Control System Implementation in Nuclear Power Plants Worldwide: A Literature Survey
N. Khan (UOIT)
Tripmap Generation for McMaster Nuclear Reactor
K. Stoll (MacU)
Hardware-in-the-Loop (HIL) Nuclear Power Plant Training Simulation Platform Design and Validation
D. Rankin (UWO)
