2016: Annual Conference of the Canadian Nuclear Society | Proceedings of the Canadian Nuclear Society

Mitigation Strategies of Beyond Design Basis Accidents (BDBA) in a CANDU Nuclear Power Plant

Rene Marcoux, Bing Li, George Arvanitis, Ali Etedali-Zadeh, Petri Hotari, Rob Dunn

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Craft – Control Room Accident Filtration

Axel Hill, Marina Welker, William Cooper

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Feasibility Study Reviewing the Use of CO₂(G) as a Tracer Gas for Leak Detection in Generators

Alex G. Page, Geoff Klempner, David McNabb, Wade Trefry, Sushank Saha

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Advances in Materials Evaluation for the Canadian SCWR Core Concept

Wenyue Zheng, David Guzonas, Kevin P. Boyle, Y. Zeng, Jian Li, Michael Greenwood, Selcuk U. Kuyucak, S. Xu

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Constructing a Grain Boundary Sensitization-Embrittlement Map for Type 310S Stainless Steel Fuel Cladding in the Canadian SCWR Concept

Y. Jiao, Q. Wang, Wenyue Zheng, David Guzonas, Mark R. Daymond, Joey Kish

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Oxide Dispersion Strengthened (ODS) Steels for CANDU Supercritical Water-Cooled Reactor (SCWR) Fuel Cladding

Selcuk U. Kuyucak, B. Shalchi Amirkhiz, Carlo Tesone

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Current Regulatory Guidance and Proposed Methodology for External Flooding Assessments

Peter Nimmrichter, Caitlin O'Grady, Elizabeth Alderson

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Towards a Unified Approach to Fire Safety in Nuclear Power Plants

T. Shiblaq

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Development Methodologies for Nuclear Safety Display System

J.H. Kim, S.M. Baek, J.H. Cho, C.H. Kim, S.D. Sohn, J.H. Yoon

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Measurements and Simulations of Weld Residual Stresses for Feeder Dissimilar Metal Welds

Y. Shi, X. Duan, M. Wang, M. Li

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Creep Properties and Tem Characterization of 347h Stainless Steel

B. Shalchi Amirkhiz, S. Xu, Jie Liang, Catherine Bibby

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Development of a Canmetmaterials Gen IV Materials Property Database for Materials Selection

Michael Greenwood, S. Xu, Wenyue Zheng

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Benchmarking MAAP-CANDU V4.0.7b With Gothic 7.2B: Response of Containment Models to Flashing and Condensation

Morgan J. Brown, Y.S.S. Chin, Samuel Gyepi-Garbrah

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MAAP5-CANDU Development

John R. Kennedy, Peter Maka, Michael Chai

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Assessment of Surveillance Tests Used to Estimate Backup Instrument Air Capacity

Cullen H. Adam, Arvind Misra

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Evaluation of External Hazards for Point Lepreau Nuclear Generating Station

Alina Nainer, Eman Elewini, Liliana Comanescu, Paul Santamaura, D.S. Mullin, A. Jean

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The Travesty of Discarding Used CANDU Fuel

Peter Ottensmeyer

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Synthetic Fuel Production via Carbon Neutral Cycles With High Temperature Nuclear Reactors as a Power Source

Evan Konarek, B. Coulas, J. Sarvinis

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Hatch Microgrid Controller for Integration of Very Small Modular Reactors With Off-Grid Power Systems

R. Rand, M. Mitchell, B. Gihm, M. Sedighy

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A Phased Approach to Human Factors Integration – Point Lepreau EME Deployment Case Study

Adam Smith, S. Boucher

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Outreach and Engagement Activities to Support Nuclear Conversatons

Matthew T.J. Dalzell, Neil R. Alexander

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Exploit the Performance of the Localization Algorithm for Wireless Sensor Networks Under Gamma Radiation

Yu Liu, Karen Colins, Liqian Li

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Implementation of a Dominant Modes Solver in Dragon

S.R. Housseiny Milany, Guy Marleau

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Sensitivity and Uncertainty Analysis of the SCWR Core Along Its Cycle With the Inclusion of Control Blades and Burnable Absorbers

J.R. Sharpe, A. Buijs

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Application of Position-Dependent Delayed-Neutron Fractions to IQA Calculations for PT-SCWR

Qingjie Liu, Eleodor Nichita

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Theoretical Research of Weak Neutron Source Induced Bursts in Fast Neutron Reactor

Jianjun Liu, Ruo-gu She

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Applications of Nuclear Safety Probabilistic Risk Assessment to Nuclear Security for Optimized Risk Mitigation

Sean K. Donnelly, Stan B. Harvey

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Conditional Probabilities of Pressure Tube Rupture During Limiting Design Basis Transients at Reactor Early Life and Late Life

Christopher C.S. Manu, Danny H.B. Mok, Dan Pun-Quach

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Guidelines for Implementing Design Extension Conditions Due to Seismic Hazards in CANDU Nuclear Power Plants

Ayman Saudy, Medhat Elgohary

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Key Technical Issues When Developing Probabilistic Foundation Input Response Spectra for Seismic Analysis

Jeffrey K. Kimball, Jose E. Blanco, Wei Li, Sean Ni, Richard Chen, Ming Han, D.S. Mullin

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Seismic Fragility Analysis of a Nuclear Building Based on Probabilistic Seismic Hazard Assessment and Soil-structure Interaction Analysis

Rosaiba Gonzalez, Sean Ni, Richard Chen, Ming Han, D.S. Mullin

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Advanced Passive Cooling Solutions for Enhancement of Safety in Nuclear Power Plants

Matthias Reuter, Leo Ornot, Christoph Schuster, Antonio Hurtado

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Implementation of Enhanced Severe Accident Management Guidance at Opg and Bruce Power

Jim Morris, Michael Huang, Ronald Henry, Sean K. Donnelly, William Tse, Ravi Patel, Lovell Gilbert

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Development and Implementation of a Severe Accident Management Program for NRU

Andrew Fitchett, Derek Burns, G. Douglas

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Validation of the Minimum Staff Complement for the NRU Reactor

Yasamin Dadashi, Nastaran Dadashi, Kathy Hughes

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IAEA Activities in Plant Life Management

J.H. Moore

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Impact of Support Gaps on the Dynamic Response of Components

Aman Usmani, Sadath Malik

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Building Interimend-state Strategy Assessment for Pickering Storage-with-surveillance

Paul J. Dinner, E. Abdalla, Jane Clemo, Mike Grey, Karl Heimlich, Charles A. Negin

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Structural Integrity Analysis for Exposure to Elevated Temperatures in the Point Lepreau Irradiated Fuel Bay

Hesham Mohammed, Waleed Mekky, M. Moland, D.S. Mullin

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A Mechanistic Model to Predict Fuel Channel Failure in the Event of Pressure Tube Overheating

A.R. Dion, John C. Luxat

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Study of Transient Neutronic-thermalhydraulic Coupling: A Case Study Using a Backbone Interface

Yu Liu, Tao Xu

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The Casualidad Method for Uncertainty Evaluations of Best-Estimate Code Calculations

A. Petruzzi

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Radiation by the Numbers: Developing an On-Line Canadian Radiation Dose Calculator as a Public Engagement and Education Tool

Matthew T.J. Dalzell

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Used Fuel Management in Canada, Finland and Sweden – Similarities and Differences

Kristina Gillin

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Upgrade of Nuclear Power Plant Laundry Waste & Floor Drain Water Treatment System Utilizing Microfiltration

Kal Farooq, Wendy Walker

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Development of Pc-based Radiological Consequence Assessment Tool for EMErgency Response to Nuclear Accident in Northeast Asia

S.H. Lee, J.Y. Kim, J.Y Kim, S.H. Kim, T.B. Yoon, L.C.C. Po

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RELAP5 Experiences and Applications for Heavy Water Reactor Technology at Nine

A. Petruzzi, M. Cherubini, D. DeLuca

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Loss of Coolant Accident Simulation With RELAP5/scdapsim/mod4 for the Canadian Supercritical Water-cooled Reactor

M. Lou, David R. Novog, C.M. Allison, R.J. Wagner

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Measurement of Transient Critical Heat Flux in a Heated Tube at Intermediate Pressures in Water

B. Statham, David R. Novog

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Use of Fission Chambers for Monitoring Neutron Flux for the First Start-ups of the Refurbished Bruce a Reactors

Charles Olive, Derek Luth, Philippe Paquette, Todd Stroud

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Vacuum Drying Strategies for CANDU Power Plants

Steve Fernandes, Mayank Singh

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Investigation on Pressure Drop Oscillation in Natural Circulation System Using Cathare

Chuanxin Peng, Yuanfeng Zan, Jianjun Xu, Yanping Huang, Wenbin Zhuo

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Coupling RELAP5 and Pressure Tube Deformation Models to Analyze the Thermal-Mechanical Phenomena in CANDU Severe Accidents

F. Zhou, David R. Novog, L.J. Siefken, C.M. Allison

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Traceability and Mathematical Modeling of Cross Correlation Flow Measurement

A. Gurevich, A. Lopez

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Range Extension From -7.0 to -7.2 Decades for Flux Monitoring Using Reactor Regulating System (RRS) Ion Chambers at Bruce Power

Charles Olive, O. Shaikh, Kwok Tsang, Philippe Paquette, Fang Bao

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Practical Considerations for Prevention of Flow Accelerated Corrosion During Refurbishment

J. Jo, P. Ferdowsi

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First Approach to Critical (ATC) for Bruce Units 1&2 Following Refurbishment

Charles Olive, Derek Luth, Philippe Paquette, Todd Stroud

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Small Modular Reactors for the Production of Hydrogen Fuel at Remote Sites

Evan Konarek, J. Eastick, B. Gihm, J. Sarvinis

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Design and Development of a Tritium-Compatible Electrolyzer

M. Rabbani, P. Ozemoyah, J. Robinson, H. Li, H. Boniface, S. Suppiah

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An Approach to Evaluate the HCLPF Capacities in the Modification Design of Sscs

H. Min, R. Li

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An Alternative Strategy for Thermodynamic Evaluations of Experimental U-Me Phase Diagrams to Resolve Considerable Experimental Discrepancies

Matthew H. Kaye, Lian Wang

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U-Ru-Rh-Pd Quaternary System: Thermodynamic Calculations and Experimental Explorations

Matthew H. Kaye, Lian Wang

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First Principles Molecular Dynamics Studies of Oxygen Sub-lattice Melting in Thoria

Barbara Szpunar, Jerzy A. Szpunar

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