2012: Annual Conference of the Canadian Nuclear Society | Proceedings of the Canadian Nuclear Society

Yeong-Kook Oh, J.G. Kwak, Y. Chu, K.R. Park, Y.S. Bae, H.K. Kim, H.L. Yang, S.W. Yoon, Y.M. Jeon, J. Kim, S.H. Hahn, W.H. Ko, J.Y. Kim, S.G. Lee, W.C. Kim, M. Kwon

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Fuelling Effect of Tangential Compact Toroid Injection in STOR-M Tokamak

Takumi Onchi, Yelu Liu, Mycola Dreval, David McColl, Tomohiko Asai, Sean Wolfe, Chijin Xiao, Akira Hirose

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A Study on the Gaps and Pathways to a Fusion DEMO

Hyuck Kim, Won-jae Choi, Changwoo Park, Hyung Kim

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Physics Optimization of the Canadian SCWR Core: Device-Free Reduction of Core Power Peaking Factors

Jeremy Pencer, Nihan Onder

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Experimental Study on Supercritical CO₂ and Development of Heat Transfer Correlation for Bare Vertical Tube

Sahil Gupta, Prabu Surendran, Igor Pioro

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Uncertainties of Reactivity Calculations with Respect to Nuclear Data for the Canadian SCWR

Laura Blomeley, Jeremy Pencer

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Used CANDU Fuel Waste Consumed and Eliminated: Environmentally Responsible, Economically Sound, Energetically Enormous

Peter Ottensmeyer

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A Controllability Study of TRUMOX Fuel for Load Following Operations in a CANDU-900 Reactor

David A. Trudell

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Development of the FAST Code for Modeling CANDU Fuel

Andrew Prudil, Brent J. Lewis, Paul K. Chan

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Experimental and Simulation Study of the Response of a Boron-Loaded Plastic Scintillator to Neutrons and Gamma-rays

Nafisah Khan, Rachid Machrafi

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Requirements for Extending the FAST Code for Transient Simulation of Nuclear Fuel

Andrew Prudil, Brent J. Lewis, Paul K. Chan

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The Dissolution Rate Constant of Magnetite in Water at Different Temperatures and Neutral or Ammoniated Chemistry Conditions

K. Mohajery, Derek H. Lister

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R & D Project of Small-to-Medium Reactor for Multipurpose Use of Energy

Tomohiko Ikegawa, Koji Nishida, Masayoshi Matsuura, Kumiaki Moriya

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Properties of Recycled Fuels

Barbara Szpunar, Jerzy A. Szpunar

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Roles of Intergranular Delta-Hydrides in the Failure of Hydrided Zr Alloys

Wen Qin, Jerzy A. Szpunar

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Effect of Surface Roughness on the Oxidation and Hydriding Behaviour of Zircaloy-4

Hamed Akhiani, Jerzy A. Szpunar

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A Review of Candidate Ceramic Materials for Use as Heat Shield Tiles in a Supercritical-Water-Cooled-Reactor

Peter McClure, Blaine Geddes, Xiao Huang, David Guzonas

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Modelling Material Effects on Flow-Accelerated Corrosion in Primary CANDU Coolant and Secondary Reactor Feed-Water

P. Phromwong, Derek H. Lister, S. Uchida

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Effects of Grain Size and Specimen Size on Small Punch Test of Type 316L Austenitic Stainless Steel

Ming Song, Wen Qin, Jerzy A. Szpunar, Kaishu Guan

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Microstructural Evaluation of Stressed IN625 and NiCrAlY Coated IN625 Tested in High and Low Density SCW

Austin Selvig, Xiao Huang, David Guzonas

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Evaluation of Oxides Formed at High Temperature in Zr-2.5Nb Pressure Tubing

A.P. Kiran Nimishakavi, Jerzy A. Szpunar

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Draft CSA Standard on Environmental Risk Assessments at Class 1 Nuclear Facilities and Uranium Mines and Mills

Donald Hart, Nava C. Garisto, Rina Parker, Ryan Kovacs, Brett Thompson

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Radiation Protection as Part of a Uranium Mine Pre-Feasibility Study

Ernest Becker, Aslam Ibrahim

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Water Quality Benchmarks, the Modifying Effect of Organic Matter on Uranium Toxicity and Why This Matters

Peter M. Chapman, Melanie A. Trenfield, Rick A. Van Dam

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A Preliminary Study on H2O2 Reactions on SIMFUEL with Different Doping Elements

Linda Wu, David W. Shoesmith

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Resolving the Concerns About the Dynamic Responses of CANDU In-Core Flux Detectors

Jerry Cuttler, Harmeet Gill, Richard Scrannage, Philippe Paquette

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An Ab Initio Study of Hydrated Nickel(II) Hydroxy Complexes

Liwei Cheng, Jane Ferguson, Cory C. Pye

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Accelerating ROP Detector Layout Optimization

Doddy Kastanya, Barbu Fodor

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Confirming Competence of Operators - A Regulatory Approach to Fuel Cycle Facilities

Martin Vesely, Justin Sigetich

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AREVA's Innovative Solutions for Valve Diagnostics and In-Situ Valve Repair

Holger Damies, Reinald Agethen, Louisa Munoz, Frank Kostroun

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NRX to Pickering

Lorne G. McConnell

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Approach Adopted by RPC Radiy for the Verification and Validation of FPGA Based Platforms for Nuclear Safety Applications.

Vladimir Sklyar, Sergio Russomanno

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HITACHI Security Concept for Industrial Control Systems

Hiromichi Endoh, Tsutomu Yamada, Satoshi Okubo, Toshihiko Nakano

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DCS Innovation by SIL and Non-SIL Unified Architecture - Hitachi Approach on G-HIACS (R800FS/R900)

Toshiki Shimizu, Yu Horikoshi, Yusaku Otsuka, Masashi Suenaga, Sunao Masunaga

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A Simple Estimate of Production of Medical isotopes by Photo-neutron Reaction at the Canadian Light Source

Barbara Szpunar, Chary Rangacharyulu, Schin Date, Hiro Ejiri

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Integration of CATHENA Thermal-hydraulic Model with CANDU 6 Analytical Simulator Controller

Majid Borairi, Hooman Javidnia, Dave Wallace, Joe Tseng, Vincent Lau, Florentin Caracas

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Steam Generator Cleanliness Management A Comprehensive Concept for CANDU Plants

Christoph Stiepani, Steffen Weiss, Georg Kraemer, Andreas Drexler, Joerg Fandrich

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Implementation of Genetic Algorithm Technique for Solving ROP Detector Layout Optimization Problem

Doddy Kastanya, Barbu Fodor

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7th CNS International "Steam Generators to Controls" Conference - A Compliment to the Remarkable CNS ‘OM+DM Utility Engagement Initiative’

Bill Schneider

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A Quick Acting Device for Arresting Incidental Gross Leakage of Heavy Water during In-Service Inspection of Coolant Channels

Amit Haruray, Manojit Bandyopadhyay, R.K. Puri, Manjit Singh

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Comparison between Surface Heating and Volumetric Heating Methods inside CANDU Reactor Moderator Test Facility (MTF) Using 3D Numerical Simulation

Araz Sarchami, Nasser Ashgriz, Marc Kwee

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Experimental Investigation of Pool Boiling Heat Transfer and Critical Heat Flux on a Downward Facing Surface

Marko Gocmanac, John C. Luxat

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Critical Heat Flux Variations on Surface of a CANDU Calandria Tube

Azin Behdadi, John C. Luxat

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Preliminary Results for Validation of Computational Fluid Dynamics for Prediction of Flow through a Split Vane Spacer Grid

Alex Rashkovan, David R. Novog

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Compilation of Supercritical Heat Transfer Data Through the IAEA Cooperative Research Program

Laurence K.H. Leung, K. Yamada

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Moble Tritium Removal Facility - An Affordable Option?

Peter Ozemoyah, John Robinson

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Testing and Monitoring of Radiologicals in Drinking Water

Brenda Stanek, Wo Yuen, Dave Chorney

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Administrative Limits for Tritium Concentrations Found in Non-Potable Groundwater at Nuclear Power Facilities

Rina Parker, Donald Hart, Cecile Willert

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Importance of the Aquatic Detritus Foodweb in the Transfer of Radionuclides From Water to Higher Trophic Levels

Glen Bird

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Advanced Technologies for Radioactive Waste Characterization and Free Release Measurement

Anton Vetrov, Petr Sladek, Valeriya Verbitskaya, C.M. Allison

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Evolution of RFSP 3.5 for CANDU Analysis

Wei Shen, P. Schwanke

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Toward Developing a Next Generation Computer Code for Fuel Analysis

Ki-Seob Sim, George S. Xu, Gong Chen, Girma G. Chassie, Masoud Shams

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Large Break LOCA Uncertainty Quantification for Boiling Natural Circulation Reactor using Latin Hypercube Sampling

A. Trivedi, A. Srivastava, Hemant G. Lele, Ashok Khanna, Prabhat Munshi, C.M. Allison

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Fukushima Type Severe Accident Analysis of Laguna Verde Nuclear Power Plant using RELAP5/SCDAPSIM

A.K. Trivedi, Ashok Khanna, Prabhat Munshi, C.M. Allison

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CANDU Fuel Attribution Through the Analysis of Delayed Neutron Temporal Behaviour

Madison T. Sellers, E. Corocoran, David G. Kelly

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The Influences of Ultrasonic Peening Treatment on Oxidation of Designed F/M Steels in Supercritical Water

Z. Liu, Jing-Li Luo, Weixing Chen, M. Li, W.Y. Zheng, David Guzonas

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Molecular Dynamics Simulation of Zirconium and Zirconium Hydride

Ravi Kiran Siripurapu, Barbara Szpunar, Jerzy A. Szpunar

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Turbulent Velocity Measurement of Rectangular Sub-channel Mixing Using Laser Doppler Velocimetry

F. Pineiro, K.H. Leung

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Monte Carlo Simulation of a Burnup-Averaged 78-Element Canadian SCWR and Similarity Study with the ZED-2 Test Reactor

Stephanie Langton, Adriaan Buijs, Ting Zhu, David R. Novog

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Fuel Composition Optimization in a 78-Element Fuel Bundle for Use in a Pressure Tube Type Supercritical Water-Cooled Reactor

David W. Hummel, David R. Novog

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Potential Resistance of Alloy 82 Dissimilar Metal Welds to Primary Water Stress Corrosion Cracking

Suraj Y. Persaud, Roger C. Newman

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Photon Mass Attenuation Coefficients of Importance to Dosimetry

Cody Crewson, Chary Rangacharyulu

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Computational Tabulation of the Spatial Origin of Scoring Secondary Electron Tracks in a Wallless Tissue Equivalent Proportional Counter under Photon Irradiation

Fawaz Ali, A.J. Walker, Edward J. Waller

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A Method for Simulating Real-Time Neutron Populations, Materials and Geometries Using the GEANT4 Monte Carlo Toolkit

L. Russell, Guy Jonkmans, Adriaan Buijs

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Material Properties of a Dissimilar Metal Weld Inconel 600/ Inconel 82 Weld Filler/ Carbon Steel (Gr. 106 B)

Steven Knapp, Xinjian Duan, Arnaud Weck

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Heat Transfer Study on Supercritical CO2 Flow in Vertical Tube

Sahil Gupta, Prabu Surendran, Igor Pioro

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Tritium and Impurity Removal from a Liquid Pb-Li Blanket

R. Yari, P. Schwanke, Matthew H. Kaye

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Optimization of Radio-Opaque Personal Protective Fabric by Monte CarloSimulation

M. Roeterink, F. Lavoie, E.G. Dickson, Emily Corcoran

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Design of the GLARE Tool A Grease Lubrication Apparatus for Research and Education

B. Rawlings

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Evaluation of Stress Corrosion Cracking of 316L Stainless Steel in Supercritical Water Using Constant-Load C-Ring Samples

Bryce Raoul, William G. Cook

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Improving the useful life of a 37-element fuel bundle

Corey French, Paul K. Chan, Stephane Paquette, Jordan Morelli, Madison T. Sellers

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An Investigation of Electrostatically Deposited Radionuclides on Latex Balloons

Terry Price, Adam Caly

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Removing Fuelling Transient Using Neutron Absorbers

Stephane Paquette, Paul K. Chan, H.W. Bonin, A. Pant

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Sensitivity Analysis of CFD Code Fluent-12 for Supercritical Water in Vertical Bare Tubes

Amjad Farah, Patrick Haines, Glenn Harvel, Igor Pioro

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Neutron Production in a Spherical Phantom Abord ISS

A. Tasbaz, Rachid Machrafi

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Development of a Transparent and Deformable Two Dimensional Radiochromic Gel Dosimeter

P. Ataei, K. Daimond

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SLOWPOKE-2 Gamma Dose Experiment

E. Pruszkowski, C. Bruuslsema

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Stainless Steel 316 corrosion testing at sub- and supercritical water conditions: An insight into the pH effect

R. Carvajal-Ortiz, I.M. Svishchev, David Guzonas

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Variable Axial Power Profile Heat-Loss Analysis of a CO2 Gas Insulation Re-entrant SCWR Fuel-Channel

Jeffrey Samuel, Glenn Harvel, Igor Pioro

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Dynamics and structure of iron hydroxide in high temperature and supercritical water

Yuan Liang Meng, I.M. Svishchev

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The Effect of Testing Direction on DHC Growth Rate Using a Zr-2.5Nb Plate

Sean Hanlon, Scott Read, Alain Douchant, Mona Primeau, Ken Kidd, Glenn Wilson, Glen A. McRae, Christopher Coleman

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Characterization of Excel Alloy Pressure Tube Material for CANDU SCW Reactors

M. Sattari, R.A Holt, Mark R. Daymond

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Heavy Ion Irradiation Effects in Zr Excel Alloy Pressure Tube Material

Y. Idrees, Z. Yao, M. Sattari, Mark R. Daymond

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Production of Molybdenum-99 by Heterogeneous and Homogeneous Uranium Fueled Reactors

George E. Carlin, H.W. Bonin

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Progress on the Development of a Look-up Table for Trans-critical Heat Transfer in Water-cooled Heated Tubes

H. Zahlan, D.C. Groeneveld, S. Tavoularis

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Assessment of Uncertainty in Full Core Reactor Physics Calculations Using Statistical Methods

C. McEwan

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Effects of Grain Size and CeO2 Addition on the Corrosion Behaviour of Cr2O3 based Ceramics in High Temperature Supercritical Water Environment

Renfei Wang, Ziqiang Dong, Wenyue Zheng, David Guzonas, Jing-Li Luo, Weixing Chen

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Temperature Dependence of Radiation-Induced Corrosion of Stellite-6 at pH 10.6

M. Behazin, J.J. Noel, Jungsook Clara Wren

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Electrochemical and Surface Study of the Oxide Growth and Conversion on 316L Stainless Steel

Quintin W. Knapp, Jungsook Clara Wren

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Effect of Phosphonium-based Ionic Liquids on the Corrosion of Carbon Steel under Gamma Radiation

R.P. Morco, Jiju M. Joseph, A.Y. Musa, Jungsook Clara Wren

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The Effect of Initial Iron Concentration and pH on theRadiolytic Formation of ?-FeOOH Nanoparticles

T. Sutherland, Pam Yakabuskie, Jungsook Clara Wren

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Commissioning Tests of the University of Ottawa Supercritical CO2 Facility

K. Jiang, H. Zahlan, S. Tavoularis, D.C. Groeneveld

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Oxidation and Stress Corrosion Cracking Initiation of Austenitic Alloys in Supercritical Water

Y. Behnamian, Ming Li, Jing-Li Luo, Weixing Chen, W. Zheng, David Guzonas

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Density dependence of the spur lifetime and the 'escape' hydrated electron yield in the low-LET radiolysis of supercritical water at 400 °C

S. Sanguanmith, L. Mirsaleh Kohan, J. Meesungnoen, Jean-Paul Jay-Gerin

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Cleaning-Up Abandoned Uranium Mines in Saskatchewan's North

Laurier L. Schramm

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