Published: 2009-05-31

Articles

Large-LOCA Margins in CANDU Reactors - An Overview of The COG Report

A.P. Muzumdar, Daniel A. Meneley
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Power Reactor Safety Comparison - a Limited Review

Daniel A. Meneley, A.P. Muzumdar
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Nuclear Criticality Safety Management for Enriched Fuel Handling Operations at Bruce Power

H.G. Austman
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Implementation of a Nuclear Criticality Safety Program at AECL

L. Dunn
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Laser Peening to Mitigate Stress Corrosion Cracking of Nuclear Power Facilities

John Rankin, Chanh Truong, C.B. Dane, F. Harris, Lloyd Hackel
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Parameters Controlling Hydrogen Ingress During Corrosion of Pressure Tube Material

M. Elmoselhi, R.E. Irwin
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A Program on The Corrosion of Carbon Steel in The Presence of Water Radiolysis

Joanne Ball, David Guzonas, C. Stuart, J.C. Wren
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Effect of Magnesium on Lead Induced Stress Corrosion Cracking of UNS N08800

L. Tian, J. Luo, B. Lu, A. Palani, Y. Lu
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Novel Gadolinium Chemistry in Moderator Water

Andreas Rudolph
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Parameters Influencing Flow-Accelerated Corrosion (FAC) in The Secondary Side of Nuclear Power Plants

M. Khatibi, D.H. Lister, A. Feicht, L. Liu, S. Uchida, K. Fujiwara, T. Ohira, H. Takiguchi, K. Hisanume
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The Crystal Structure and Elastic Properties of Pure and Dy Doped Urania

B. Szpunar, J. Szpunar
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Onset of The Local Magnetic Moment on Nb in Zirconia

B. Szpunar, J. Szpunar
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The Considerations to Use Soft Start AC Controllers in Nuclear Application

D. Raonic, S. Maljukan
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Investigation into Sensitivity of Darlington Boiler 2 Feedwater Flow Calibration Factor to Boiler Level Control Valve Configuration

D. Coppens, Yuri Gurevich, V. Ton, D. Zobin
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Display Concepts for Maintaining Alarm State Overview During Unit Evolutions

E. Davey
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Liquid Zone Control System Instability Test Program

L. Rodrigo, H. Boniface, G.D. Zakaib
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A Distributed Control System Design for Nuclear-Based Hydrogen Production With Copper-Chlorine Thermochemical Cycle

A. Al-Dabbagh, L. Lu
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Advanced Digital Rod Position Indication System for Existing and Next Generation Nuclear Reactors

H.M. Hashemian, G.W. Morton, B.D. Shumaker
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Darlington NGS Vacuum Building Outage: Modification to Supply Post-Seismic Makeup Water to The Heat Transport System

Doris Li, B. Dean, M. Emad
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Qualification and Performance of An Improved Inflatable Seal for Containment

T. Sykes
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Pickering Unit 7 Calandria Tube Leak Operational Impacts

J. Price, R. Powell
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Maximum Allowable Crack Size for Cracks in The Attachment Weld of Nuclear Steam Generator Upper Lateral Support Lugs

S.-Y. Yang, A. Sze
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Characteristics of Wear Products From Fueling Machine Ram Balls at Darlington

Aamir Husain, C. Wu, Y. Verzilov
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Stochastic Modeling of Inspection Uncertainties and Applications to Pitting Flaws in Steam Generator Tubes

D. Mao, X.-X. Yuan, Mahesh D. Pandey
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Development of a Simplified Fuel Oxidation Model for Defective Nuclear Fuel

K. Shaheen, Brent J. Lewis
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Graduate Diplomas in Nuclear Technology

George Bereznai
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Making Ionising Radiation a Real Experience for High School Science Students

Jeremy Whitlock, Peter Lang, Doug De La Matter, Paul Hinman, Bryan White
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Passive Fire Protection

T. Cerosky, V. Raillard, R. Smith
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A Web-Based Resource for the Nuclear Science/Technology High School Curriculum

C. Ripley
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AECL R & D’s Role in Promoting Nuclear Research and Eduction

R. Sadhankar
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ACR-1000® Environmental Performance Design Improvements

Melanie Sachar, S. Julien, K. Hau
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Castor Oil Polyurethane as a Coating Option for Spent Nuclear Fuel Disposal Containment

A. Mortley, H.W. Bonin, V.T. Bui
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The Future of Radioecology at AECL? Back to Basics

D. Rowan
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Design and Installation of a Strategically Placed Algae Mesh Barrier at OPG's Pickering Nuclear Generating Station

D. Marttila, P. Patrick, C. Gregoris
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Introductory Remarks to Western Focus Seminar

Duane Pendergast, Jim Harvie, Harold McFarlane
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Removal of Selected Radionuclides and Metal Contaminants by Natural Zeolites From Liquid Effluents

J. Gallant, A. Prakash, LuVerne E.W. Hogg
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Comparing the Market for Nuclear Power in Alberta and Saskatchewan

D. Bratt
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Should Manitoba Go Nuclear?

L. Simpson, B. Skinner
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Type Testing of LiF:Mg,Cu,P Extremity TLD Type Testing at Ontario Power Generation

D. Morris
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Using a Thermalhydraulics System Code to Estimate Heat Transfer Coefficients for a Critical Heat Flux Experiment

B.A. Statham
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Numerical Simulation of Heat Transfer of Supercritical Fluids Under SCWR Conditions

Y. Zhang
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Comparative Studies of Digital Controllers in CANDU Nuclear Power Plants

Poland Zahedi, Elyad Zahedi
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Isotope Effects on Apparent and Partial Molar Volumes of HCl, LiCl, and NaCl Measured in H2O and D2O from 250 C to 350 C and 14 MPa to 19 Mpa

K. Erickson, S. Moore, D. Raffa, L. Trevani, P. Tremaine
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Predicting Iron Transport in a Supercritical Water Cooled Pressure Tube Reactor

F. Brosseau, David Guzonas, P. Tremaine
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Critical Control Valves and their Reliability During Seismic Events

Poland Zahedi, Elyad Zahedi
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Development of Design Support Tool Using Integrated Hierarchical Control Chart (HCC) & IEC61131 for Nuclear Power Plant Control

Elnara Nasimi, H. Gaber
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Validation of The TRIAD3 Code Used for The Neutronic Simulation of The NRU Reactor

Timothy Leung, Mike Atfield
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Neutronic Modeling and Thermal Neutron Flux Measurement of The MCR6 Rod in The NRU Reactor

X. Wang, Timothy Leung
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SORO Prediction of High Response NOP Detectors

G. Wang
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Application of RFSP-IST Determined Trip Delay Time to Wolsong-1 Loss of Regulation Simulations

Dai-Hai Chung, J.-H. Kim, C.-H. Cho, S.M. Kim
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Review of Worldwide Reactor-Physics Codes and Their Applicability to CANDU® and ACR-1000® Analysis

W. Shen, M. Dahmani
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MINER: Three-Dimensional Multi-Group Finite-Difference and Nodal Method for CANDU® Applications

B. Phelps, W. Shen, Elisabeth Varin
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Correction in Homogenization Method for CANDU Fuel Channel Deformation

G.-S. Choi, M.-H. Kim, J.H. Park
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A Simulation-Based Optimization of The Secondary Loop of Gentilly-2 Nuclear Power Plant

J. Dipama, W. Hounkonnou, Alberto Teyssedou, F. Aubé
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Heat Transfer Modeling of CANDU Pressure Tube Under Localized High Temperature Condition

Farshad Talebi, John C. Luxat
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A Mechanisitic Model for Pressure Tube-Calandria Tube Thermal Contact Conductance for a Pressure Tube Ballooning Event

A. Cziraky, John C. Luxat
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2D Modeling of Moderator Flow and Temperature Distribution Around a Single Channel After PT/CT Contact

Azin Behdadi, John C. Luxat
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Applicability of Steady State Critical Heat Flux Data to Transient Processes

Liqun Sun
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Flow Oscillation Simulation With CATHENA

Liqun Sun
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An Assessment of Pressure Tube Rupture Event in The Refurbished Wolsong-1 Nuclear Power Plant

S.R. Kim, B.J. Moon, J.Y. Huh, C.J. Choi, D.S. Lee, S.M. Kim, Y.S. Lee
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MAAP4-CANDU Application to The PSA Level 2 for The Point Lepreau Nuclear Generating Station Refurbishment Project

S. Petoukhov, M. Brown, M. Mathew
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History of ROP Margins Erosion and Power Recovery at Gentilly-2

O. Vagner, M. Nguyen, G. Hotte
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Human Factors Considerations in RD-337: Design of New Nuclear Power Plants

Felicity Harrison
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Exploration of Pressure Tube Ballooning Temperature

Liqun Sun
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Gentilly-2 Internal Initiating Events Frequencies Estimation for Level 1 PSA: The Need for Shared Generic CANDU Frequencies

Khaled Joober, A. Bellil, J-F. Bolduc, T. Houasnia, Raynald Vaillancourt
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Level 1 Internal Flood PSA Accident Sequence Quantification for Point Lepreau Refurbishment Project

M. Wei, S. Sawh, Liliana Comanescu, B. Lee, J.G. Ha, Raj Jaitly, A. Jean, D. Basque, D.S. Mullin
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Bruce Power's Nuclear Pressure Boundary Quality Assurance Program-Requirements, Implementation and Transition

J.C. Krane
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Integrating Risk Management and Safety Culture in a Framework for Risk Informed Decision Making

William R. Nelson
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Managing Organizational Culture Within a Management System

L. Comeau, G. Watts
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Evaluating Safety Management System Implementation

M. Preuss
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Development of a Risk-Informed Safety Management System at The Gentilly-2 Nuclear Generating Station

Dragon Komljenovic, G. Hotte, M. Beaudet
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Experiences from the Incorporation of International Rules and Guidelines on the Safety of Nuclear Power Plants into the German Nuclear Rules and Regulations

C. Wassilew, R. Donderer, M. Mertins
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Predicting and Preventing Organizational Failure: Learning, Stability and Safety Culture

Romney B. Duffey
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Nuclear Safety Culture at Pickering A: "Post ISTB"

M. Elliott
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Integrated Management System Laying a Foundation for Excellence

S. Brissette, D. Vincent
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Recent IAEA Activities to Support Advanced Water Cooled Reactor Technology Development

Jong-Ho Choi, Sama Bilbao Y León, Atambir Singh Rao
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Hitachi Turbine Generator Technology for Nuclear Applications

T. Nakamura, T. Kudo, Naoki Akane
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CAREM: An Innovative-Integrated PWR

R. Mazzi
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Recent Results of Research on Supercritical Water-Cooled Reactors in Europe

Joerg Starflinger, Christina Koehly, Thomas Schulenberg, Csaba Maraczy, A. Toivonen, S. Penttila, L. Chandra, J.-A. Lycklama a Nijeholt
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Canada's NSERC/NRCan/AECL Generation IV Energy Technologies Program

D. Brady, T. Anderson, David Guzonas, H. Khartabil, Laurence K.H. Leung, S. Quinn, W. Zheng
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Thermalhydraulics Projects in Support of Conceptual Design and Safety Analyses of CANDU SCWR

Laurence K.H. Leung
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Predicting Risk and Human Reliability: A New Approach

Romney B. Duffey, T.S. Ha
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Advanced CANDU Reactor, Computer-Based Displays Design Process

R. Bodner, R. Chatterton
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Using Statistical Process Control Methodology to Improve the Safe Operating Envelope

D. Reeves, P. Lunney, M. McIntyre, R. Prime
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Implementing Maintenance Complement Changes and Experience With Regulatory Guide G-323

K. Berntson, J. Budau
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Applicability of Small Fast Reactor "4S" for Oil Sands Recovery

S. Matsuyama, Y. Nishiguchi, Y. Sakashita, S. Kasuga, M. Kawashima, T. Grenci
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Compact, Transportable Nuclear Power Systems For Rapid Deployment To Remote Locations For Industry, Oil Recovery, Municipalities And Disaster Relief

J.R. Powell, J.P. Farrell, G. Merkel
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Plasma Electrolytic Oxidation (PEO) Coatings on a Zirconium Alloy for Improved Wear and Corrosion Resistance

Y. Chen, X. Nie, D. Northwood
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Dysprosia Doped Uranium Dioxide Fuel and the Lambda Transition

M. Kleczek, Brent J. Lewis, W.T. Thompson
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Sheath Hydriding Model for Defective Fuel

G. Bruni, Brent J. Lewis, W.T. Thompson
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Communication Networks and their Applications in Control Systems of Nuclear Power Plants

A. Al-Dabbagh
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Multi-Step Approach to Code-Coupling for Progression Induced Severe Accidents in CANDU NPPS (MACPISA-CANDU)

D. Pohl, John C. Luxat, W. Giannotti, F. D'Auria
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Towards Implementing Direct Sensitivity and Uncertainty Methods in Thermalhydraulic Codes

Andrew C. Morreale
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Investigation into the Application of Polyetherimide to Nuclear Waste Storage Containers

Y. Saboui, H.W. Bonin, V.T. Bui
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A Preliminary Evaluation of Elemental Constituents of the Degraded Motor Engine Oil Using Neutron Activation Analysis

M. Murphy, R. Machrafi
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The Future Nuclear Vision

D. Torgerson
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Institutional Failure: Are Safety Management Systems The Answer?

John G. Waddington, J.F. Lafortune, Romney B. Duffey
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On The Difference Between DRAGON and WIMS-AECL Calculations of The Coolant Void Reactivity

Dimitar V. Altiparmakov, Danila Roubtsov, D. Irish
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Comparison of MCNP and WIMS-AECL / RFSP Calculations With High Temperature Substitution Experiments in ZED-2 Using CANFLEX-LVRF

Jeremy Pencer, Blair P. Bromley, David G. Watts, Paul Carlson, Alex Rauket, Michael B. Zeller
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Reactor Physics Code Suite Validation Using Station Start-Up Data: An Assessment of Feasibility

I. Beith, G. Gavrus, Y. Parlatan, Mohamed Younis
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Monte Carlo and Deterministic Evaluations of Pressure Tube Creep in a CANDU Lattice

Y. Kim, Gyuhong Roh, S.T. Hong, J.H. Park
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Test Irradiation of Recycled Uranium in Chinese CANDU Reactors

Yongjun Jiao, Dongsheng Li, Mingjun Chen, Zhiliang Meng, Jun Wang, S. Kuran, C. Cottrell
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Assessment of The Coarse-Mesh Finite-Difference Method With The Multicell Methodology in RFSP for ACR-1000®

W. Shen, B. Phelps
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Validation of RRS Emulator Against Pickering B Setback Event

D. Luxat, Z. Farooqui, M. Dobrean, B.G. Phan, L. Blake
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Optimisation of CANFLEX-SCWR Bundle Through Subchannel Analysis

J. Shan, Laurence K.H. Leung
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A Validation of CATHENA Fuel Channel Model for a Post Blowdown Analysis Against a High Temperature Thermal-Chemical Experiment Cs28-2

B.-W. Rhee, H.T. Kim, J.H. Park, J.Q. Shan
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Compliance Strategy for Statistically Based Neutron Overpower Protection Safety Analysis Methodology

E. Holliday, B.G. Phan, Ovidiu Nainer
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Evaluation of ASSERT-PV V3R1 Void Fraction Predictions Against The OECD/NEA BFBT Benchmark Data

K. Leung, David R. Novog
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Advanced Design of ACR-1000® Moderator System

W.Y. Wang, J. Zhang, R. Noghrekar, R. Aboud, K. Hau, M. Soulard
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Using FORTRAN Modules to Design and Develop Modular Reactor Analysis Software Components

M. Mwaba
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ACR-1000® Pre-Project Regulatory Review Progress

N. Popov, R. Ion, S. Doerffer, J. Hopwood
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CANDU 6 HTS Diagnostic and Adjustment System for Economic and Safety-System Optimization

W.J. Hartmann, H. Choi, D.J. Wallace, Victor Caxaj, A. Elalami
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Injection Transition Analysis of PLGS MPLP ECC System

Zhenhua Cui, M. McIntyre, R. Prime, P. Lunney
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The Use of “Grading” in the Application of the CSA N286.7 Standard for Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants

J. Pascoe, D. Richards, E. Mileta, J. Skears
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Enhancement of The Moderator Subcooling Margin Using Glass-Peened Calandria Tubes in CANDU Reactors

H.Z. Fan, R. Aboud, P. Neal, Thambiayah Nitheanandan
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An Engineering Primer on Extreme Value Statistics

David R. Novog, Fred Hoppe, Ovidiu Nainer, B.G. Phan
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Pickering NGS Unit 7 Gadolinium Oxalate Formation Event: Investigation and Recovery

E. Sorin, David Buchan
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Pressure Tube and Calandria Tube Volume Reduction for Large Scale CANDU Retube

G. Hersak
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Practical Examples of how Knowledge Management is Addressed in Point Lepreau Heat Transport Ageing Management Programs

John Slade, Tracy Gendron, G. Greenlaw
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A Risk-Informed Approach to The Assessment of DHC Initiation in Pressure Tubes

A.K. Sahoo, Mahesh D. Pandey
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A Probabilistic Approach to Update The Lower Bound Fracture Toughness Using Surveillance Pressure Tube Data

Mahesh D. Pandey, M. Wang
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Bruce Units 3 and 4 Life Extension Integrated Safety Review Process and Lessons Learned

D. Duncan, L. Watt, J. West, P. Chan
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Feeder Grayloc Hub Local Allowable Thickness - An Application of FFSG Appendix E Level 2 Evaluation

M. Li
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Integrated Ultrasonic Inspection Technology to Meet The Requirements of CANDU Steam Generator

A. Chen, K. Maynard, K. Chan, T. Malkiewicz, J. Prince, J. Huggins
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Environmental Assessment Overview for New Build Reactors

G. Bird, A. Hayton, W. Lai
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Toxicity Regulation of RLW Effluent From CANDU Stations - Lessons From Ontario's MISA Program

D. Rodgers
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Modelling of Radiation Exposure at High-Altitudes During Solar Storms

Hani AlAnid, Brent J. Lewis, L.G.I. Bennett, M. Takada
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Spent Fuel Storage Bay Cooling System, Modelling and Analysis

Alex Gidi
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Setting Priorities for Decommissioning and Remediation Activities under The Federal Nuclear Legacy Liabilities Program at AECL Sites

M.E. Stephens, J.L. Campbell, D.H. Charlesworth, S.H. Miller, C.A. Purdy, C.W. Turner
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Creep and Shrinkage Analysis for Concrete Spent Fuel Dry Storage Module

D. Zhang
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Development of a Digital Amplifier for Nuclear Radiation Detectors

S. Yue, T. Rector, B. Sur
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Evaluation of Slow Shutdown System Flux Detectors in Point Lepreau Generating Station - I: Dynamic Response Characterization

Vinicius N.P. Anghel, Daniel Comeau, J. McKay, Bhaskar Sur, D. Taylor
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Evaluation of Slow Shutdown System Flux Detectors in Point Lepreau Generating Station - II: Dynamic Compensation Error Analysis

Vinicius N.P. Anghel, Bhaskar Sur, D. Taylor
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DCS Emulator Development for Nuclear Power Plants

Y. Nakashima, K. Ishii, D. Chiba
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Design of a Portable Antineutrino Detector for Nuclear Reactor Monitoring

A. Ip, A.B. McDonald, Guy Jonkmans, B. Sur
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Implementation of Control Logic for Mitigating Systems in DCS

S. Narisetty-Gupta, A. Xing, J. Harber
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Design of a Decoupling Algorithm for The Reactor Nodal Core Model of a Large PHWR

N. Khan, L. Lu
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Qualifications Needed to Design, Construct and Manufacture Nuclear Systems and Equipment

C. Voutsinos
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Energy Research and Public Policy Advice: A Bridge to Canada's Future

L. Hoye
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Nuclear Energy And Health: And the Benefits of Low-dose Radiation Hormesis

J.M. Cuttler, M. Pollycove
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Towards Improving the Detection Limit of Electron Paramagnetic Resonance (EPR) Dosimetry of Drywall

R. Mistry, J. Thompson, J. Rink, Douglas R. Boreham
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Heated Downward Facing Steel Plate in Pool Boiling

R. Lin
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Study of Trace Depressurization Predictions for the Marviken Critical Flow Test

David Hummel
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WIMS Simulation of SCWR CANDU Geometry

M. McDonald
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Best Estimate SBLOCA Analysis of CANDU 9 Systems Part I: CATHENA Modelling

Fang Bao
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An Approach to Modelling of Intermittent Buoyancy Induced Flow

J. Spencer
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Effects of Two-Phase Mixing and Void Drift Models on Subchannel Void Fraction Predictions in Vertical Bundles

K. Leung
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Mining and Its Tailing: The Environmental and Radioecological Consequent in Nigeria

I. Musa, B.A. Adewumi, A. AbdulGaniu
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