2017: Annual Conference of the Canadian Nuclear Society | Proceedings of the Canadian Nuclear Society

Generation of Heat Transfer Coefficient Profiles for Three Correlations at Various Operating Conditions

Hakim Maloufi, A. Zopf, H. Xie, W. Anderson, C. Langevin, Igor Pioro

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Review of Margins Beyond Design Basis Earthquake

Aman Usmani, Tarek Aziz

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Verification of the Dyadyakin and Popov Heat Transfer Correlation using Experiment Data for 3-Rod Bundles

Hakim Maloufi, A. Zopf, H. Xie, W. Anderson, Igor Pioro

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Effect of Missing Mass and Rigid Motion on Seismic Response Spectrum Analysis

Yuxin Liu, X.M. Han, Lingam Vaithlingam, Wei Jiang

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A Review of Flow Accelerated Corrosion in CANDU Feeder Pipes

Uditha Wijayaratne, George Bereznai, Sharman Perera

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The Importance Of Microstructural Characterization Of Copper Coatings On Used Fuel Containers For Long-Term Disposal Of Canada's Nuclear Waste

W.L. Li, J.G. Giallonardo, J.T. Tam, P.L. Lin, D.D. Doyle, G.P. Palumbo, U.E. Erb

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Dosimetric Characterization of an Accessory Mounted Mini-beam Collimator Across Multiple Clinically Beam-matched Medical Linear Accelerators

W. Davis, G. Cranmer-Sargison, Chary Rangacharyulu, A. Alexander, V. Kundapur

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AREVA – Aging Management Software Platform

Andre Zander, Thomas Seitz, Udo Wildner

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Multi-Objective Sarapan and Dermaga Algorithms for Generating Random Patterned-Channel-Age in CANDU Fuel Management Analyses

D. Kastanya

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Investigation of the Lattice Physics Phenomena in the Canadian PT-SCWR Within Some Perturbed Scenarios

A. Moghrabi, David R. Novog

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SCWR Water Chemistry: Proto-cracks and Hydrogen Oxidation

D.T. Kallikragas, K.I. Choudry, I.M. Svishchev

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Study of Local Fuel Temperature Distribution Effects Using Coupled Lattice Physics and Thermal Hydraulics Codes

Adam Eckhardt, In Seob Hong, Mohamed Dahmani

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Analytic Benchmark for Fuel-Reflector PHWR Configurations

Peter Schwanke, Eleodor Nichita

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Minimization of Lift-off Effects on Gap Measurements Using Optimal Frequencies

Perryn Bennett, G. Klein, M. Luloff, P.R. Underhill, J. Morelli, Thomas W. Krause

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ELORA: The Canadian Nuclear Fuel Simulation

K.F. Ansillo, John C. Luxat

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Evaluation of Chf Correlations for Nonuniform Axially Heated Tubes in Steam Generator

N. Almalki, W.H. Ahmed

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Benchmarking of the Transient Reactor Physics Simulation Code: G4-STORK

M. Ponce Tovar, Adriaan Buijs, D.R. Dovog

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Dynamic Response of Two-Phase Flow Through Piping Component With Flow Restricting Orifice

O. Bamidele, W.H. Ahmed, Marwan Hassan

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Vibrational Behaviour and Natural Frequencies of a CANDU Fuel String

Mohammad Fadaee, Shudong Yu

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Reactivity Initiated Accident for the Canadian SCWR

Frederic Salaun, David R. Novog

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The Role of Sulfur and Lead in the Corrosion of Nickel Alloys Relevant to Nuclear Steam Generators

A. Foroozan, Anatolie G. Carcea, Roger C. Newman

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Partridge-II – an International Research Program for Developing a Probabilistic Tool for Risk-Informed Decision Making

Xinjian Duan, Khalid Chaudhry, Rob McLean, Nikola Popov, L. Sun, Krish Krishnan

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Simulation With Trace of a BWR/4 Steam Line Break Under "Hot Standby" Conditions

Y. Aounallah

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Investigation of the Factors Affecting Stress Corrosion Cracking Rates in Zircaloy-4 Foil

Evan Veryard, Z. Wang, Mark R. Daymond, D. Wowk, Emily Corcoran

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Comparative Reactor Physics Study on Accident-tolerant Fuel for the CANDU Reactor

S. Younan, David R. Novog

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Simulation of a CANDU 6 Containment Leakage Rate Test Using Melcor

H.C. Kim, S.K. Pak, J.S. Lee, S.W. Cho

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Trouble Shooting Leakage Issues in a Dry Storage Container (Dsc)

Jim Carmichael, T. Iqbal, Catherine Wang, James A. Sato

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The Component Operational Experience, Degradation and Ageing Programme (CODAP) Project; Canada's Contributions and Capabilities of the Program

Harishan Manoharan, J. Riznic

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Utilizing Simulation and Experiment for In-core Gamma Heat Estimation of the McMaster Nuclear Reactor

Mohammed Alqahtani, Adriaan Buijs

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Interaction of NpO₂⁺ With Cl^- in Na-Ca-Cl Type Solutions With High Ionic Strength

Shinya Nagasaki, Takumi Saito, S. Tsushima, J. Goguen, T. Yang

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Quantom - a New Methodology for Scanning of Unopened Nuclear Waste Packages

A. Havenith, J. Kettler, K. Krycki, H. Wiesel, S. Wegener, W. Cooper

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An Educational Tool for Pressurized Heavy Water Reactor Burnup Analysis

Ralph Laite, M. Naraine

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Evaluation of Effect of Temperature Variation on Pressure Tube to Calandria Tube Gap Measurements

G. Klein, J. Morelli, Thomas W. Krause

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Improvements in Rfsp Prediction Capability for Spatial Control in Darlington Reactors

Galina LeRoy, Aaron Sullivan

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Core Elements Improvements for Optimization of Radioisotopes Production in an MTR-type Core

T. Makmal, Mohammed Alqahtani, S.E. Day, Adriaan Buijs, John C. Luxat

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Adjuster Shim Operation at Darlington: Using Configuration-Specific Reference Maps

Constantin Banica, Aaron Sullivan, Yuksel Parlatan, Ross Rock

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Subcritical Reactivity Calculations

E. Talbot

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Study of Zr-2.5Nb-0.5Cu CANDU Spacer Material: Microstructure and Irradiation Effect

Qinshan Dong, Hongbing Yu, Zhongwen Yao, Mark R. Daymond

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Verification of Hydrogen Corrosion Probe (HCP) Operability Under Feedwater Chemistry Conditions

J. Kongtuk, William G. Cook, Derek H. Lister, F.R. Steward, T. Rirksomboon

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Combustion Simulation of Transportation Package Performance in Severe, Long Duration Fire Using Computational Fluid Dynamics Tools

Y. Sui

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C-14 – Recovery From Spent Resin

Peter Zeh, Andreas Stahl, Luis Sempere Belda, William H. Cooper

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Evaluation of the Effect of Construction Material on the Accumulation of Hydrogen in CNER's Hydrogen Corrosion Probes (HCPS)

P. Santiwiparat, Derek H. Lister, F.R. Steward, William G. Cook

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Measurement and Simulation of Dividing Manifolds for Moderator Flow Test Facility

C.W. Hollingshead, David R. Novog

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Nuclear Waste Retreatment / Retrieval – Concepts and Technologies

S. Nothvogel, T. Maeck

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The Application of the Portable Nuclide Recognizing Rapid Radiation Distribution Monitoring System for Ensuring Radiation Safety

U. Lee, H.R. Kim

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Evolution of an Alloy 690 Surface During Oxidation in a Simulated Pwscc Environment

Ali Eskandari, D. Artymowicz, S. Ramamurthy, Roger C. Newman

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Synergistic Effects Between Radiation Chemistry and Carbon Steel Corrosion in the Calandria Vault and End Shield Cooling System of a CANDU Reactor

Jordan Lyons, William G. Cook, C. Stuart, E. Gardner

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Design Considerations of Cooling Towers for the Darlington B. Nuclear Generation Station Potential New-Build

Jiaqi Zhao, Peter Dolloso, Kayshiva Maharaj, Saud Farhat, George Bereznai, Daniel Hoornweg

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Susceptibility of Alloy 800 to Stress-corrosion Cracking Investigated in Caustic Solutions at High-temperature and High-pressure Conditions

Mariusz Bryk, D. Artymowicz, Anatolie G. Carcea, Roger C. Newman, A. Korinek, G.A. Botton

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Use of Helmholtz Resonators to Suppress Acoustic Pressure Pulsations in Pipelines

Moamen Abdelmwgoud, Mahmoud Shaaban, N. Arafa, Karim Sachedina, Atef Mohany, Marwan Hassan

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Human Error Assessments for Implementing Severe Accident Management Strategies Using a Dynamic HRA Method

S.H. Jang, M.S. Jae

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A Comparison of Cs-137 and X-ray Sources as Calibration References for Thermoluminescent Dosimeter Chips Used in the Saskatchewan Postal Quality Assurance Program for Diagnostic Radiology

Arvind Ravichandran, J. Sadowski

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Fuel Behaviour After a Loss of Coolant in an Irradiated Fuel Bay

Derek Logtenberg, Paul K. Chan, Emily Corcoran

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Nano-Slacle Mechanical Test of Irradiated X-750 Ni-Based Superalloy

P. Changizian, C. Lu, Z. Yao

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Improvement of Safety Parameters in the CANDU Reactor Using Burnable Absorber Erbium

Mohammad Abdul Motalab, W. Kim, Younghee Kim

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Research on Thermal Efficiencies of Various Power Cycles for GFRS

Roman Popov, Mohammed Mahdi, Igor Pioro

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Literature Review of Cladding for Corrosion Protection of Structural Alloys in Molten Fluoride Salts

C. Eveleigh, Joey Kish, John C. Luxat

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Kernel Density Estimation Method in Time-Dependent Monte Carlo Simulation

W. Yan

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Updated Shielding Analysis Methodology Applied to OPG Waste Management Facilites

Philip Smith, Omar Shaikh, Paul Crowley

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Educating the Public About Radiation Using Inexpensive, Easy to Make Scintillator Detectors

J. Hanania, Jason Donev

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Effect of Ni and Cr Contents on Corrosion of Steel Under Reactor Condition

J. Shin, D. Guo, D. Li, Jungsook Clara Wren

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The Economics of Novel VSMR in the North

M. Moore

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Optimization Approach of Energy Group Structure for the Canadian Pressure Tube Supercritical Water Reactor

A. Moghrabi, David R. Novog

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Gendering Analyses of Social License to Operate in Saskatchewan's Nuclear Sector

Jacqueline S. Schoenfeld, Kalowatie D. Doenandan

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Decision Matrix for the Waste Processing of Spent Ion-exchange Resin From Nuclear Power Plants

Julie Kim, B.M. Ikeda, J. McKellar

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Analysis of the Efficiency of Electromagnetic Pump for Sodium Thermohydraulic Test According to Cooling Condition

J.S. Kwak, H.R. Kim

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Who's Listening? Stakeholder Dialogue as seen by Stakeholders

Ellen Lloyd, M. Bourassa

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Fusion Related Experimental Studies at the University of Saskatchean

Chijin Xiao, S. Elgriw, Akbar Rohollahi, R. Behbahani, J. Adegun, Michael Patterson, S. Chung, O. Mitarai, Akira Hirose

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The Development of an Agile Analysis Method to Support the Conceptual Design of the Rolls-Royce Small Modular Reactor

Christopher Bennett, David J. Baker, Jon Coulson, James Archer, Sam Treasure

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Ionic Strength and Ph Dependence of Sorption of Pd onto Illite, Bentonite, and Shale

A. Walker, J. Goguen, J. Riddoch, Shinya Nagasaki

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An Exploration of Interactive Teaching Tools for the Use of Nuclear and Astrophysics Education

M. Bootsma, Jason Donev

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Self Powered Neutron Detectors Calculations Using RAST-K 2.1

F. Khoshahval, M. Park, J. Park, J. Choe, P. Zhang, H.C. Shin, J.E. Jung, H.S. Lee, D. Lee

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Investigation of the CANDU Fuel Bundle Structural Integrity Due to Flow-Induced Vibrations

O. Elnanhawy, Mohamed Alziadeh, Atef Mohany, Marwan Hassan

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Numerical Modeling of Turbulent Mixing in Connected Nuclear Fuel Subchannels with Appendages

M. Ballyk, M.F. Lighstone, S. Tullis

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Quantitative Raman Investigation Of Uranyl Sulfate Complexation Under Hydrothermal Conditions

C.D. Alcorn, J.S. Cox, L.M.S.G.A. Applegarth, P.R. Tremaine

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From Burial to Recycling: a Change Imperative for Nuclear Fuel Waste Management

F. Peter Ottensmeyer

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Coupled Hydro-Mechanical Behaviour of In-Situ Shaft Sealing Components

Chang Seok Kim, Marolo C. Alfaro, James A. Blatz, David A. Dixon

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Boric Acid Ionization Constants and Triborate Formation Constants under PWR Primary Coolant Conditions by AC Conductivity

J.P. Ferguson, Hugues Arcis, D.H. Hussey, Daniel M. Wells, P.R. Tremaine

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Comparison of Heat-transfer Correlations Based on Forced-convection Data Obtained in R-22 and R-134a at Supercritical Pressures

Nicholas Tarsitano, K. Sidawi, Igor Pioro

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CANDU Spent Fuel Purification

Saloni Sabharwal, C. Wei, Jiawei Le, Lucas Pereira, Sam Cherniak, Cullen Adam, A. Foroozan, Eric Jelinski

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Environmental Radiation (ENRAD) Sampling Robot

Andrea Bellingham, R. Nandakumar, R. Sharpe, S. Valookaran, T. Ravindran, Sharman Perera, Edward J. Waller

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Experimental Study on Flow Instability and Critical Heat Flux of Two Parallel Channels

XiaoZhong Liu, ChuanXin Peng

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An Evaluation of Cliff-Edge Effect Under SBO and Loss of EPS System Combined With Loss of UHS for the Aged CANDU-6 Reactor

E.K. Jang, S.R. Kim, S.D. Yi

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The Effects OFPH and Radiation on Corrosion and Oxide Formation on Pure Nickel at 80°C in Buffer Solutions

R.K.H. Karimi Haghighi, Jungsook Clara Wren

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Sorption Modelling of Th(IV), Np(IV), and Np(V) on Illite and Montmorillonite

J. Goguen, Shinya Nagasaki

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Post-Dryout Heat Transfer Assessment of Trace

Y. Aounallah

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Sensitivity Studies for the Station Blackout Accident With Crash-Cooldown at a Generic 900 Mw CANDU Reactor

F. Zhou, David R. Novog, Christopher Harwood

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Corrosion of Copper Coated Nuclear Waste Containers by Nitric Acid Droplets

J. Turnball, R. Szukalo, M. Behazin, D. Zagidulin, S. Ramamurthy, Jungsook Clara Wren, David W. Shoesmith

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Modeling of Radiolytic Production of Oxidants Relevant to Corrosion of a Used Fuel Container in Deep Geologic Repository Environments

R.P. Morco, Jiju M. Joseph, David W. Shoesmith, Jungsook Clara Wren

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Stability Threshold of a Loosely Supported Triangle Tube Array Subjected to Crossflow

A. Elhelaly, Atef Mohany, S. Moussa, Marwan Hassan

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Optimization of Time-Average Calculations in CANDU Fuel Management Using Simulated Annealing: Minimization of Maximum Bundle and Channel Powers

Doddy Kastanya, Darryl McClure

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H2o2 Humid Air Radiolysis-induced Corrosion of Carbon Steel - Stainless Steel Welds

M. Zakeri, M. Momeni, Jiju M. Joseph, O. Yong, Jungsook Clara Wren

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Atomistic Simulations of Dislocations in Zirconium Alloys

Cong Dai, P. Saidi, L. Balogh, Y. Zao, Mark R. Daymond

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Monte Carlo Fixed Source Calculations to Support Bruce Power Start-Up Instrumentation Preliminary Design

Jingliang Hu, Emile Talbot, Anas Khaial, Philippe Paquette, Mohamed Dahmani

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Comparison Between Wims-Aecl Depletion Calculations and a PWR Thorium Pin-Cell Burnup Benchmark

Tony Liang, Mohamed Dahmani

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Radiolytic Copper Corrosion: Mechanism of Cu2O Growth

M. Naghizadeh, A.M. Jean, M. Momeni, Jiju M. Joseph, G. Whitaker, Jungsook Clara Wren

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Design Process and Build of an Automated Neutron Spectrometer Concept

Natasha Galipeau, Mudit Nijhawan, Sharman Perera, Carson Roberts, A. Waker

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Application of Bayes Method in Evaluation of Rop/nop Trip Setpoint

Dumitru Serghiuta, J. Tholammakkil, A. O'Hagan, D.A. Stephens

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RPS an Opportunity to Expand Canadian Involvement in Space

J.J. Alho, B.R. Megaw, Jason Donev

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Integrated Framework for Propagation of Uncertainties in Nuclear Cross-Sections in CANDU Steady-State and Transient Reactor Physics Simulations

Hany S. Abdel-Khalik, Dumitru Serghiuta, J. Tholammakkil, A. Trottier

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Cycle Length Extension of SMPWR Using Zircaloy Reflector

J. Choe, H.C. Shin, J.E. Jung, H.S. Lee, D. Lee

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Preliminary Flux Measurements at the McMaster Nuclear Reactor

E.L. MacConnachie, David R. Novog, S.E. Day

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Videoconferencing as a Method of Doing Nuclear Outreach Across Canada

D.M. Grelowski, J.L. Owen, Jason Donev

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A Reliability Assessment for the Decay Heat Removal System in the Sfr Using Reliability Physics Model

Jintae Kim, Moosung Jae

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A Small Modular PWR Core Design Using Nitride Fcm Fuels With Fecral Cladding for Natural Circulation

D.H. Hwang, J.Y. Choi, S.G. Hong, W.J. Lee, F. Venneri

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The NuScale Power Module Small Modular Reactor and Its Potential Applications to Canada

C.P. Rintoul, D.M. Grelowski, Y. Huang, Jason Donev

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GEANT4 Simulations of Prompt Neutron Detection Using Neutron Time-Correlation Methods

Abigail Gaulin, F. Ali, L. Li, G. Li, G. Bentoumi

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A SMR PWR Reactor Core Design Using Nitride Fcm Fuels With Fecral Cladding and Forced Convection Circulation

J.Y. Choi, D.H. Hwang, S.G. Hong, W.J. Lee, F. Venneri

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Integrated Approach to Fluoride High Temperature Reactor (Fhr) Technology Development

Farzad Rahnema, Bojan Petrovic, Preet Singh, X. Sun, P. Tsvetkov, G. Yoder, Dingkang Zhang, J. Zhang

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Neutronic Modeling of Molten Salt Reactors

U. Shahid, M.A. Allaf, F.O. Ozkan, A. Yilmazer

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Embalse Steam Generator Replacement Project: Main Challenges and Progress Update of the Implementation Phase

P.J. Luna, J. Jesko, Stefan Bostelaar, R. Sainz

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Quantifying Probe Coverage Error in Feeder Thinning Assessment

Mikko I. Jyrkama, M.D. Pandey

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Managing Material Degradation in Nuclear Power Plants

Mike Montazer, Danyal Montazer

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Challenge Performing CANDU Fuel Channel Reactor Maintenance on Aging CANDU Reactors

T. Lake

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Using Plasma Technology as a New Proven Development for Treating Radioactive Waste on an Industrial Scale

Jan Deckers

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Performance of On-The-Fly Cross Sections Processing in Monte Carlo Simulation Code

Jack Yu, Hyunsuk Lee, K. Azamat, K. Wang, D. Lee

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Microdosimetric Studies in Mixed Neutron and Gamma Ray Fields Using Triple Gem Tissue Equivalent Proportional Counters

Marat Seydaliev, J. Dubeau

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Swift Heavy Ion Irradiation of Zirconium Alloy: Deleterious Effects on Thermal and Mechanical Properties

S. Kong, R. Bai, Z. Hua, W. Wang, L. Liu, D. Yuan, H. Ban, H. Xia

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Minimizing Public Radiation Dose at Decommissioned Mine Sites for Future Land Use Opportunities

J. Shen, J. Tang, R. Parker, D. Hart

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Development of Measurement Technology for Beta-Ray Depth Distribituion in Soil

J.W. Bae, U. Lee, C.W. Lee, H.R. Kim

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Selection of Objective Functions in the Multi-Objective Fuel Management Optimization

F. Khoshahval, D. Lee

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Distributed Temperature Measurements Along a Heated Tube Using All-Fiber Bragg Grating Optical Sensors

Robert C. Bowden, W. Li, Michel Gaudet, Ben Benson, Ali Siddiqui

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Dynamic Reliability Analysis of a Digital Control System

Chireuding Zeliang, Hossam Gaber

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Radon Progeny Identification and Rejection Based on Pseudo Coincidence Technique – Feasibility Analysis

A. Caly, Eugene Saltanov, G. Bogorodzki

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Status Update: Elevated Radiation Fields in the Primary Heat Transport System at the Point Lepreau Nuclear Generating Station

William Cook, Glen Brown, B. Smith, E. Gardner, Paul D. Thompson

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