2010: 31st Annual Conference of the Canadian Nuclear Society | Proceedings of the Canadian Nuclear Society

G. Li, D. Lascar, Anthony Levand, Marisa Pedretti, G. Savard, Dariusz Seweryniak, K.S. Sharma, J. Van Schelt, M.G. Sternberg, T. Sun, A.H. Wuosmaa, G. Gwinner, Sidney Gulick, Nicholas Scielzo, Ralph Segel, Peter Bertone, Fritz Buchinger, S. Caldwell, A. Chaudhuri, J.A. Clark, John Crawford, C.M. Deibel, J. Fallis, Raymond Yee

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Best Estimate SBLOCA Analysis of CANDU 9 Systems Part II: Control System Modelling

Fang Bao

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Effects of Gamma Radiation Versus Peroxide on Carbon Steel Corrosion

K. Daub, X. Zhang, James J. Noël, J. Clara Wren

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The Phase Transport and Reactions of γ-Irradiated Aqueous-Ionic Liquids

S. Howett, J. Joseph, S. Peiris, Z. Ding, J. Clara Wren

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Theoretical and Experimental Analysis of Ultrasonic Cross Correlation Flow Measurement Technology

A. Gurevich, S. Selvaratnarajah, Ibrahim Abdalla

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Corrosion of Ag-Ag2O in Iodide Solutions: A Potential Radioiodine Immobilization Route

S. Pretty, P.G. Keech, X. Zhang, J. Clara Wren

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An Electrochemical Study Of H2O2 Decomposition on Single-Phase α-Fe2O3 Films

Dong Fu

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The Effect of Interfacial Mass Transfer on Steady-State Water Radiolysis

Pam Yakabuskie, J. Joseph, J. Clara Wren

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Neutronic Analysis of an Incorporated Thorium - Uranium Breeder-Booster in CANDU-6

Bradford Holmes, Mohamed Geweida

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Synthesis and Characterisation of a Lithium Ferrite Electrode for Nuclear Reactor Applications

M. Manley, William Cook

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Application of Neutron Diffraction in Characterization of Texture Evolution during High- Temperature Creep in Magnesium Alloys

Anton Sediako, Scott Shook, Sven C. Vogel, Dimitry Sediako

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Heat Transfer in a Bundle Cooled with Supercritical Freon-12

Wargha Peiman, Ashley Milner, Caleb Pascoe, Hemal Patel, Graham Richards, Igor Pioro

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The Effects of Surface Mechanical Attrition Treatment (SMAT) on the Electrochemical and Surface Properties of Alloy 600

M. Faichuk, S. Ramamurthy, W.M. Lau

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System Study of CANDU/LWR Synergy in Advanced Nuclear Fuel Cycles

Yonni Friedlander

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Thermal-Elastic Deformation of CANDU Pressure Tube Following Fuel Element to Pressure Tube Contact

Farshad Talebi, Azin Behdadi, John C. Luxat

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Qualification of a Computer Program to Analyze Shutdown System Flux Detector Response in Point Lepreau Generating Station

Quincy Alexander, Vinicius N.P. Anghel, Daniel Comeau, Milan Ducic, Roxana Hutanu, Guy Jonkmans, Jonathon McKay, Bhaskar Sur, Dean Taylor

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Physics Analysis on the NRU Core for an Accident Scenario of a Loop Pressure Tube Crack

Timothy Leung

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Experience with WOLSONG-1 Phase-B Pre-Simulations Using WIMS/DRAGON/RFSP-IST Code Suite

Dai-Hai Chung, Bong Ghi Kim, Sung Kim, Hyung-Bum Suh, Han-Sang Kim, Hyung-Jin Kim

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Inverse Kinetics For Subcritical Systems with Variating External Sources

Cristiano Silva, Daniel A.P. Palma, Alessandro C. Gonçalves, Aquilino S. Martinez

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Fuel-Pin Flux Reconstruction for CANDU Applications

Mohamed Dahmani, Wei Shen, Brian Phelps

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Neutron Diffusion Waves In CANDU Reactors

Vinicius N.P. Anghel, Guy Jonkmans, Dimitar V. Altiparmakov, Bhaskar Sur

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Models For Resonance Self-Shielding Calculation in Neutronic Analysis of the CANDU-SCWR Fuel Channel

Genevieve Harrisson, Guy Marleau

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Numerical Simulation of Cross-Flow in Tube-Bundles to Model Flow Circulation of the Moderator in CANDU-6

Romain Necciari, Alberto Teyssedou, Marcelo Reggio

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CNSC Expectations for Resolution of the Hydrogen Safety Issues

Magda Rizk, Alexandre Viktorov

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Qinshan CANDU 6 Main Heat Transport System High Operational Performance

Wolfgang Hartmann, Chun Zeng, Jinjun Feng

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NUCIRC Thermal-Hydraulic Applications in Support of CANDU® Plant Design and Operation

Asmae Elalami, Wolfgang Hartmann, Arian Espahbod, Mohammad Tochaie

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Comparison of Turbulent Models for CANDU® Moderator Following a Pressure Tube To Calandria Tube Contact

Azin Behdadi, John C. Luxat

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Computational Fluid Dynamics Model for Liquid Poison Injection in the ACR-1000® Design

Fei Song, Reza Noghrehkar, Leslie Morris, Ken Hau

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Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Jong Ho Choi

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CNSC Power Reactor Operating License Reform

Ken Lafrenière

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An Approach for Risk Informed Safety Culture Assessment for Canadian Nuclear Power Stations

William R. Nelson

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Risk-Informed Decision-Making in Canadian Nuclear Regulation

George Ishack

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Safety Analysis: Its Role and Current Trends

Alexandre Viktorov

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Application of the CNSC Risk-Informed Decision-Making Process in Nuclear Power Regulation: An Example

George Ishack

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Impact of Flow Accelerated Corrosion (FAC) on Feeder Refurbishment Planning

Mikko I. Jyrkama, Mahesh D. Pandey

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The Experience of Safety System Refurbishment in Wolsong Unit 1

Jung Lee, I Hwang, Jin Huh, Tae Park, Deuck Lee, Dong Nam, Eui Hwang

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Initiation Phase of the Nuclear Refurbishment at Darlington Nuclear Generating Station

Marina Freire-Gormaly

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Condition Assessment of Installed Nuclear Power Plant (I & C) Cables

K. Anandakumaran

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A Containment Analysis for SBLOCA without ECI in the Refurbished Wolsong-1 Nuclear Power Plant

Techmo Kim, Bokja Moon, Changjoon Bae, Seonghee Lee, Chuljin Choi, Deuck Lee, Sung-Min Kim

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Gentilly-2 CANDU Nuclear Power Plant level 1 Fire and Flood PSA -- Insights on a Work in Progress

Khaled Joober, C. Selman, J-F. Bolduc, A. Nava Dominguez, A. Bellil, T. Houasnia, Raynald Vaillancourt

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Localized Thinning Assessment - Service Life Extention for Darlington Feeders Feeders

Ming Li, Jason Van Wart, Irfan Haq

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Portable Gamma-Ray Spectrometry for Decommissioning: Anywhere, Anytime, Anything

Michael Attas, Ernie Bialas

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Predicting the Time Course of Radionuclides in Aquatic Food Webs Following Pulse Releases

David J. Rowan

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Best Available Technique (BAT) Assessment Applied to ACR-1000® Waste and Heavy Water Management Systems

Melanie Sachar, Serge Julien, Ken Hau

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Protecting Fresh Water Resources during a Large-scale Low-Level Radioactive Waste Clean-up Project with Best Available Technology

Gary Vandergaast, Glenn Case

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Making Strides on the Port Hope Area Initiative: Canada’s Largest Low-Level Radioactive Waste Clean-up Project

Christine Fahey, Glenn Case

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Use of Compound-Specific Isotope Analyses as a Tool to Demonstrate Biodegradation of Petroleum Hydrocarbons in Contaminated Groundwater

Daniel Bouchard, Patrick Hohener, Daniel Hunkeler

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Human Health Risk Assessment for Radiological and Chemical Contaminants at Site with Historical Contamination

Nava C. Garisto, Farrah Cooper, Rebecca Peters

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Optimization of Power-Cycle Arrangements for Supercritical Water Cooled Reactors (SCWRS)

Laure Lizon-A-Lugrin, Alberto Teyssedou, Igor Pioro

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Canada's Used Nuclear Fuel Waste: A 20 Trillion Dollar Energy Resource Energy Extraction and Partial Detoxification in Fast-Neutron Reactors

Peter Ottensmeyer

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Denatured Molten Salt Reactors (DMSR): An Idea Whose Time Has Finally Come?

David LeBlanc

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Draft Layout, Containment and Performance of the Safety System of the European Supercritical Water-Cooled Reactor

Joerg Starflinger, Marc Schlagenhaufer, Christina Koehly, Thomas Schulenberg, Stefan Rothschmitt, Dietmar Bittermann

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Research and Development Initiatives in Support of the Conceptual Design for the CANDU® Supercritical Water-Cooled Reactor

Daniel Brady, David Guzonas, Wenyue Zheng, Laurence K.H. Leung

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Application of the Full 3-D Collision Probability Method to Randomly Distributed Spherical Fuel Elements

Marc-André Lajoie, Guy Marleau

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Physics Experiments in the Zed-2 Reactor Using CANFLEX-RU

Julian E. Atfield, Michael B. Zeller

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Advances in the ACR-1000® Reactor Regulating System and Reactor Control

Galina LeRoy, Ron Robinson

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Probability Table Monte Carlo Method Applied to CANDU-6 Cell Calculation in DRAGON

Nicolas Martin, Alain Hebert

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Monte Carlo Simulation of Neutron Transport Applied to Criticality: Focus on Sources and Flux Convergence Issues

Joachim Miss, Yann Richet, Olivier Jacquet

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An Analytical Approximation for the Prediction of Transients with Temperature Feedback

Daniel A.P. Palma, Adilson Silva, Alessandro C. Gonçalves, Aquilino S. Martinez

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Study of Power End Peaking for NRU Loop Fuel Calculations

T.S. Nguyen, R.E. Donders

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Simulating Molten Fuel-Moderator Interactions with the Code MC3D

Jeremy Licht

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Equivalent Moderator Subcooling Methodology to Determine Fuel Channel Integrity Upon Pressure Tube and Calandria Tube Contact

Liqun Sun, Bruce Willemsen

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Heat Transfer Parameters for Glass-Peened Calandria Tube in Pressure Tube and Calandria Tube Contact Conditions

Liqun Sun, Bruce Willemsen

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The Development of Trip Coverage Maps for the McMaster Nuclear Reactor

Kurt Stoll, Simon Day, John C. Luxat

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Regulatory Oversight of Refurbishment Projects in Canada

Jeff Stevenson, François Rinfret

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Regulatory Assessment of Integrated Safety Reviews for Nuclear Plants Refurbishment

Al Omar, Christian Carrier

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Development Strategy of the Improved Standard Technical Specification for Wolsong CANDU-6 Nuclear Power Plants

Sung Kim, Hyeong Kim, Seong Choi

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Consideration of Inspection Uncertainties in the Probabilistic Assessment of Steam Generator Tubing

Mahesh D. Pandey, Dongliang Lu, Jovica Riznic

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Maintenance Optimization through Risk Based Ageing Management Program

Marie-Charlotte Barreau, Isadora Cornish-Bowden, Laurent Augé, Richard Frenette

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A Proposed Structural, Risk-Informed Approach to the Periodicity of CANDU-6 Nuclear Containment Integrated Leak Rate Testing

Nabil Saliba, Dragon Komljenovic, Luc Chouinard, Raynald Vaillancourt, Guy Chrétien, Vladimir Gocevski

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Comparison of Dose Estimate Results from Radioecological Risk Assessment Models RESRAD-BIOTA, ERICA Tool and SENES Risk Model Using a Case Study

Nava C. Garisto, Ryan Kovacs, Allison Janes

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