Published: 2006-06-11

Articles

Myths and Realities in Education and Research: the problem of knowledge and judgement in democracies

John S. Cowan
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Evaluation of Hydrogen Production Using CATHENA-ELOCA During a LOCA/LOECC Scenario

G. Sabourin, Gilbert Parent, H.M. Huynh
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Single-Phase Pressure-Drop Measurements Over Low Void Reactivity Fuel

Uditha P.M. Senaratne, Laurence K.H. Leung, F.J. Doria, J. Lau
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Characterization of Flashing Jet Aerosols With a Phase-doppler Anemometer

S. Sutradhar
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Assessment of Fluid-to-Fluid Modelling of Critical Heat Flux in Horizontal 37-Element Bundle Flows

S. Yang
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Thermodynamic and Fluid-Dynamic Properties of Water for High-temperature Nuclear Reactors

R.L. Varty
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Calibration of HPGE Well-Type Detectors Using the Direct Mathematical Method

Mahmoud I. Abbas, Sherif S. Nafee, Younis S. Selim
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Regulatory Approach for Life Extension of Nuclear Power Plants in Canada

D.G. Miller, Ian M. Grant, Ken Lafreniere, P. Webster
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Impact of Point Lepreau Nuclear Generating Station Refurbishment on New Brunswick

Syed M.H. Zaidi
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Protection of Health, Safety and Environment During Point Lepreau Refurbishment

C. Hickman, P. Wilson, L. Comeau, D. Rankin, N. Pontikakis, C. Cottrell, R. Khaloo, J. Akeroyd
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Methodology for the Control of Equipment Ageing in Nuclear Power Plants

Francis Trudel, George Abdul-nour, Raynald Vaillancourt, Dragan Komljenovic
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The Impact of Aging on Life Cycle Cost: Techniques for Analysis and Optimization

Mikko I. Jyrkama, Mahesh D. Pandey
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Leadership in the Control Room

S.J. McDougall
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Control Centre Operations as the Focus for Building Station Teamwork - Issues and Resource Impacts

Glen Mathews, Lee Lane, Eric C. Davey
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Visualized Fuelling Process and 3 Dimensional Reactivity Device and Core Monitor

Bryan Patterson, Rene Cusson, Timothy Crowell
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Design of Advanced Graphical Displays for the Turbine-generator Systems of the Forsmark 3 Simulator

Jordanna Kwok, Catherine M. Burns
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Ecological Interface Design for the Condenser Subsystems of a Boiling Water Reactor

N. Lau, G. Jamieson
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Lessons Learned in Reviewing Processes Supporting Procedural Adherence

Helen McRobbie, Jean-Yves Fiset
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The Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes

W. Li, R.A. Holt
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Texture Evolution During Compression in Zircaloy-2

F. Xu, R.A. Holt, D.A. Durance, Mark R. Daymond
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Development of Type II Residual Strains in Inconel 690 Steam Generator Materials

D.A. Durance, R.A. Holt, E.C. Oliver, R.B. Rogge
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Load Partitioning in Zr-2.5%Nb During Compression

S. Cai, Mark R. Daymond, R.A. Holt, E.C. Oliver
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Preliminary Development of Flaw Evaluation Procedures for Delayed Hydride Cracking Initiation Under Hydride Non-Ratcheting Conditions

S. Xu, J. Cui, D. Kawa, G.K. Shek, D.A. Scarth
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Deuterium Buildup in the Rolled Joint Regions of Operating CANDU Pressure Tubes

Mohammad Elmoselhi, A.A. Bahurmuz
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Strategy for 100-Year Life of the ACR-1000 Concrete Containment Structure

H. Abrishami, M. Elgohary
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A Methodology Used in Calculating Nuclear Heat Balance

K.T. Tsang
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Homogeneous Slowpoke Reactor for the Production of Radio-Isotope: a Feasibility Study

Paul Busatta, Hugues W. Bonin
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ACR Fuel Storage Analysis: Finite Element Heat Transfer Analysis of Dry Storage

Khairy Khair, Saleh Baset, Julian Millard
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Combating Obsolescence - ACR Digital Control Systems Design

Sunil Tikku, Gilbert Raiskums
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Documenting Control System Functionality for Digital Control Implementations

J. Harber, M. Borairi, Sunil Tikku, A. Josefowicz
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Aging Management Applied to Storage of Bulk Ion Exchange Resin in Epoxy Coated Carbon Steel Containers

Gloria M. Kwong
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The Influence of Temperature and Chloride/Sulphate Concentration on the Passive Behaviour of Grade-7 Titanium

D. Ofori, J.J. Noel, D.W. Shoesmith
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Stress Corrosion Cracking Mechanisms of Fe-based Alloys in Hydrogenated Hot Water

Zoe Coull
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Flow-accelerated Corrosion Modelling of CANDU Outlet Feeders

O. Silpsrikul
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Electrochemical and Corrosion Testing of Copper Nuclear Waste Canisters Exposed to Sulphide Environments

J. Smith
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Mechanism of Intergranular Corrosion of NiCu Alloys

William Zhang, Jessie Zhang
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Hydrogen Absorption Into Alpha Titanium Alloys

L. Yan, J.J. Noel, D.W. Shoesmith
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Monitoring Defective CANDU Fuel Bundles

Emily Corcoran
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Self-powered Detectors for Power Reactors: an Overview

Jianping Ma
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Improvement of the Iodine Monitoring System at McMaster Nuclear Reactor

Lobat Tayebi
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Modelling the Behaviour of UO2+x During Melting

M.J. Welland, Brent J. Lewis, W.T. Thompson
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Nuclear Power Plant Simulators for Educational Purposes

Polad Zahedi
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Validation of the CATHENA Fuel Channel Model for the Post Blowdown Analysis for the CS28-1 Experiment, I - Steady State

Bo-Wook Rhee, H.S. Kang, H.T. Kim, B.J. Min, J.H. Park
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GOTHIC-IST Model of ISP-47 Phase B Mistra Experiment

Y.S. Chin
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Validation of CATHENA Fuel Channel Model for Post Blowdown Analysis Against CS28-1 Experiment, II - Transient

Bo-Wook Rhee, J.H. Park
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Release and Deposition of Fission Products from Sheathed CANDU® Fuel Samples in Hot-Cell Experiment 5 TGT Tests

A.I. Belov, R.S. Dickson, R.T. Peplinskie, M.D. Gauthier
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Loss of Coolant Accident (LOCA) Analysis for McMaster Nuclear Reactor Through Probabilistic Risk Assessment (PRA)

Taesung Ha, William J. Garland
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Development of TUF-ELOCA - a Software Tool for Integrated Single-channel Thermal-Hydraulic and Fuel Element Analyses

A.I. Popescu, E. Wu, W.W. Yousef, J. Pascoe, Y. Parlatan, M. Kwee
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Point Lepreau Refurbishment - Update 6

Gaëtan Thomas, E.R. Eagles, J. McIntosh, R. Baker, C. Hickman, Paul D. Thompson, D.A. Scott, J. Akeroyd, N. Ichiyen
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Progress on Seismic Margin Assessment and Fire PSA for Lepreau Refurbishment

B. Lee, R. Jaitly, Liliana Comanescu, S. Aprodu, J.G. Ha, D. Mullin, A. Jean, D. Basque, Paul D. Thompson
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Human Factors on the Point Lepreau Refurbishment Project

Olivier St-Cyr, J. Scott Malcolm, Alex McDonald
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Generator Refurbishment/Replacement for Life Extension Point Lepreau Refurbishment Project

Hussein Dhirani, Navin Tailor, Alex McDonald
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Point Lepreau Refurbishment Project Programmable Digital Comparator (PDC) Replacement for SDS1 and SDS2 - Update 2 Software Development and Review and Validation Test Rig Development

K.G. Fraser, M. Zhao, Adrian Condor, Alex McDonald, Paul D. Thompson
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Environmental Assessment for Bruce Restart: Calculating Doses to Non-Human Biota

Mark Gerchikov, Michael Thorne, Badi Khan, Jimin Peng, Duncan Moffett, Jim Hilbig
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MATLAB / SIMULINK Model of Candu Reactor for Control Studies

Hooman Javidnia, Jin Jiang
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A Balanced Approach for Establishing Fire Protection Requirements for CANDU Plants

S.P. Lee, S.D. Nam
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Quality Assurance in Managing a Cable Route Database

M. An, B. Gorham, C.K. Scott
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An SME's Quality Management Experience

B. Gorham, C.K. Scott
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Gamma Spectrometry Measurements for Monitoring Activity Transport at the Nuclear Stations

Aamir Husain
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A Business Focus for Technical Support Staff

M. McIntyre, C.K. Scott
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Learning Curves in Control Rooms: Skill? Rule? Knowledge?

Romney B. Duffey, John W. Saull
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Supporting Human Performance in Operations - Principles for New Nuclear Build

Lee Lane, Eric C. Davey
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Smart CANDU - Predicting to Improve Plant Performance

C.W. Turner, R. Judd, R.F. Wichman
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Cernavoda CANDU 600 NPP - Latest in House Improvements of Main Control Room Functionality Based on Computerized Applications

Dragos Popa-Nemoiu, Daniela Nica
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Using Virtual Reality Technology to Include Field Operators in Simulation and Training

Espen Nystad, Stine Strand
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The Role of Function Analysis in the ACR Control Centre Design

R.P. Leger, Eric C. Davey
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ROP Trip Setpoints Update for GENTILLY-2 Since 2004

M. Nguyen, O. Vagner, G. Hotte
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WIMS-AECL Multicell Calculations for Burnup Heterogeneity

I.S. Hong, B. Rouben
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Decay Heat Power Comparisons Between ORIGEN-S Code and ANSI/ANS-5.1-2005 Standard

Z. Cui, C.K. Scott
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Bundle Specific Decay Heat Power Calculations by Chaos-w Code

Z. Cui, C.K. Scott, B. Gorham
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A Simple and Fast Calculation Method for CANDU Decay Heat Power

Z. Cui, C.K. Scott
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Improving the Accuracy of Neutron Flux Calculations in a CANDU Reactor by Combining the Diffusion Equation With in-Core Detector Readings

Eleodor Nichita, K. Zabienski
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Simulation of the Point Lepreau Core-Follow History With SORO

F.C. Shanes, C.G. Olive, I. Cheng, C. Banica, C. Newman, O. Nainer
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The Effect of Bubble Formation and Detachment on Magnetite Deposition on Alloy-800 Surfaces During Boiling Heat Transfer

K. Khumsa-Ang, D.H. Lister
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Electrochemical and Surface Analysis of Hydrogen Effects on Uranium Dioxide

M.E. Broczkowski, J.J. Noel, D.W. Shoesmith
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Isotope Effects on Standard and Partial Molar Volumes of NaCl, HCl and NaOH Measured in Light and Heavy Water at 250°C and 300°C

Erik Balodis, Liliana Treviani, Peter Tremaine
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Interaction of Aqueous Iodine Species With Ag/Ag2O Surfaces

Sarah Danielle Stewart
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Preliminary Study of the Effect of Dissolved Zinc in PWR Coolant on in-Core Crud Deposits

P. Srisukvatananan, D.H. Lister
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Aqueous Sodium Phosphate Hideout Reactions With Nickel and Titanium Oxides Under CANDU-PHW ​Boiler Conditions

M. Madekufamba, Liliana Treviani, Peter Tremaine
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Mixed Field Radiation Modification of Polyurethanes Based on Castor Oil

Aba Mortley, H.W. Bonin, V.T. Bui
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The Kinetics of O2 Reduction Studies on Hyperstoichiometric UO2.002 Electrode

Heming He, J.J. Noel, D.W. Shoesmith
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Investigation of Interfacing NPP Simulators With PSCAD Software

Poland Zahedi
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End Flux Peaking Study for ACR-700-Type Reactor

Abdelhamid Zkiek
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Impact of Digital Control Systems on Nuclear Power Plants

Katarzyna Zabienski
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Survey of Networked Control Systems and Their Potential Applications in Nuclear Power Plants

Abdullah Kadri
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Validation of CATHENA for CHF and Post Dryout Heat Transfer Using an RD-14M Small-Break LOCA Test

S. Liu, G.M. Waddington
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Modelling of Pressure Distributions Over Fuel-strings for Fuel Irradiation Experiments in the NRU Reactor

E. Nihan Önder, Laurence K.H. Leung
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Development of the CATHENA Fuel Channel Model for an Integrated Blowdown and Post-blowdown Analysis for a 37-Element CANDU Fuel Channel

Bo-Wook Rhee, T.Y. Shin, K.M. Yoo, Hyoung Tae Kim, B.J. Min, Joo Hwan Park
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Simulation of a CS28-2 High Temperature Experiment by Using the CFX Code

Hyoung Tae Kim, Bo-Wook Rhee, Joo Hwan Park
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Investigation of Natural Circulation Two-Phase Flow Behaviour in Header Manifold Using CFD Code

P. Gulshani
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CFD Prediction of the Inlet Nozzle Velocity Profiles for the CANDU Moderator Analysis

Churl Yoon, Joo Hwan Park
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Continuous-Flow Accelerator Mass Spectrometry for Radiocarbon Analysis

J.S.C. Wills, B.X. Han, K.F. von Reden, R.J. Schneider, M.L. Roberts
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The Investigation of UFM Application to CANDU Control

Kenji Tominaga, Tadahiro Yudate, Michael A. Cormier
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Evaluation of a Distributed Control System for Potential Applications in Nuclear Power Plants

Jin Jiang, Carlos O'Donell, Qingfeng Li
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Measurements of High-Pressure Steam-Water Enthalpy/Void Migration in Unequally Heated Horizontal Twin Subchannels

S.C. Sutradhar, S.T. Yin, R.M. Tain
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Application of the Single Failure Criterion to the Advanced CANDU Reactor (ACR)

C. Nie, A.H. Stretch, P. Santamaura, D. Wright, B. Lekakh
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Pre-licensing of the Advanced CANDU Reactor

R. Ion, N.K. Popov, V. Snell, J. West, C. Xu
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ACR-1000 Design Provisions for Severe Accidents

N.K. Popov, P. Santamaura, H. Shapiro, V.G. Snell
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ACR-1000 ECC Design Concept

B. Lekakh, D. Wright, K. Hau, Z. Bilanovic, S. Ford, T. Mahendralingam
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Distributed Control System Application to CANDU Plants Recent Activities for Adaptation of DCS Platform to IEC Standards

K. Ishii, M. Kobayashi, M. Shiraishi, S. Masunaga, H. Harada, G. Raiskums, Sunil Tikku
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Determination of the Optimal Surveillance Test Interval for Shutdown System Number 1

Sungwhan Cho, Jin Jiang
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A Human Factors Approach to Effective Maintenance

Johanne Penington, Shakib Shakeri
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Approach to CANDU Spent Resin Management

Shiv Vijayan, Pierre C.F. Wong
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Life Cycle of Carbon-14 From Nuclear Reactor Production: Global and North American Estimates

Francois Caron, Man-Sung Yim
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A Probabilistic Degradation Model for the Estimation of the Remaining Life Distribution of Feeders

X.-X. Yuan, Mahesh D. Pandey, Grant A. Bickel
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U-Bolts Used as Pipe Restraints in CANDU Nuclear Power Plant

Jerzy Czarnik
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Transition to Large Scale Nuclear Energy Supply

D.A. Meneley
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Health Effects of Low Level Radiation: When Will We Acknowledge the Reality?

Jerry M. Cuttler
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Worldwide Nuclear Industry's Views on the Evolution of International Radiological Protection Policies Proposed by the ICRP

S. Saint-Pierre
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The Importance of Building and Enhancing Worldwide Industry Cooperation in the Areas of Radiological Protection, Waste Management and Decommissioning

S. Saint-Pierre
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Management of Technical Knowledge in Strengthening the Global Nuclear Safety Regime

Chang-Sun Kang
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CNS Members Promoting Nuclear Energy in Public Debate - an Example From Quebec

J. Franta, G. Sabourin, M. Saint-Denis
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Investigation of One-Sided Radiation-based Approaches to Detection of Visually Obscured Threats

William R. Scott
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Optimal Estimation of Space-Time Kinetics Reactivity Components Using a Reference Model Approach

Daryoosh Vashaee, Lobat Tayebi
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Overview of Probabilistic Risk Assessment Methodology

Taesung Ha
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Safety Analysis of a Homogeneous Slowpoke Reactor

Rejean Luc Gagnon
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An Investigation on Enhancing Thermocouple Performance in NPPS

Fawaz Ali
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