Published: 1992-06-10

Articles

WIMS-AECL Calculations for the Doppler Coefficient of Reactivity

F.C. Wong
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Reactor Physics Aspects of Modelling In-Core Small Loss of Coolant Accidents

E.V. Carruthers, M.Z. Farooqui, A.S. Adebiyi, G. Gaboury, H.S. Smith, M.B. Gold
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ORIGEN-S Cross-section Libraries for CANDU Used-Fuel Characterization

I.C. Gauld
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An Automated Procedure for Excluding Readings of Failed Detectors in Flux Mapping

B. Rouben, H.W. Dassen, K. Ossia
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The Use of Depleted Uranium for the Reduction of Void Reactivity in CANDU Reactors

A.R. Dastur, P.S.W. Chan, D. Bowslaugh
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Description of Physics Data for CATHENA Safety Analysis of the MAPLE-X10 Reactor

P.A. Carlson, R.J. Ellis, H. McIlwain, E.F. Talbot
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The Concept of a Passive Water-cooled Tube Reactor Without Emergency Core Cooling System

Soon Heung Chang, Won-Pil Baek
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Design Concepts for Passive Heat Rejection in CANDU Reactors

J.H. Beaton, N.J. Spinks, R.F. Dam
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Uprating of CANDU Reactors - A Feasibility Study

S.S. Dua, T. Lee, J. Mistry, C. Lee
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Modem Turbine-Generators for Standardized Nuclear Power Plant

J.A. Hesketh
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The Management of Tritium Reduction at Ontario Hydro

Louis Fernandes
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D20 Production by Laser-Induced Selective Multiphoton Decomposition (MPD)

M. Ivanco, Glenn A. McRae, Robert D. McAlpine
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Fission Product Release from HEU Uranium-Aluminium Alloy Fuel in SLOWPOKE-2 Reactors

A.M.C. Harnden, Brent J. Lewis, L.G.I. Bennett
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Transport Theory Evaluation of the Release of Short-Lived Fission Products from Fuel Grains

H.E. Sills, Y. Liu
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Sheath Protection Mechanism Afforded by CANLUB

P.K. Chan, I. Aitchison, G.M. MacGillivray
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Extended Burnup CANDU Fuel: Description of Database and Comparison with Code Predictions

W.R. Richmond, J.M. Bunge, V.I. Arimescu
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Particle Size Distribution of U308 Produced by Oxidation of Fuel in Air at 300-900OC

Z. Liu, D.S. Cox, R.D. Barrand, C.E.L. Hunt
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Dissolution of UO2 Fuel by Molten Zircaloy-4

P.J. Hayward, I.M. George, M.C. Arneson
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Large Deflection 4 Elastic-Mastic Piping Stress Analysis of Feeder and Feeder Supports used in a CANDU Reactor

K. Chaudhry, S.A. Usmaui, T. Lee, C.C. Yao
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Determination of the Allowable Operating Envelope for the Point Lepreau Special Safety Systems

M.K. Gay, J.D. Kendall, J.H. McIntosh, DoF. Rennick, P.D. Thompson
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Development of a Human Factors Engineering Program for New CANDU Plant Designs

J.S. Malcolm, J. Pauksens
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NPP Technical Documentation Management - The G2 Perspective on Taming the Paper Tiger

Paul Lafrenifere
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Developments in CANDU Standard Plant Licensing

Joe F. Sobolewski, Paul S.L. Lee, Peter J. Allen
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Highlights of Canadian Activities in Fusion Safety

G.A. Vivian, A. Natalizio, M.A. Wright
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An Emerging Technology for Fusion: The Spherical Pinch

E. Panarella
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Results and Update on the TdeV Facility

G. LeClair
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Gas Chromatograph Isotope Separation for Kmfbrschungszentnun Karlsruhe GmbH

K.G. Torr
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Development of a Pressure Swing Adsorption Process for Recovery of Tritium from Solid Ceramic Breeder Helium Purge Gas of a Fusion Reactor

C. Fong, S.K. Sood, D.M. Ruthven, O.K. Kveton
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300 km/s Plasma Accelerator for Fuelling

R. Raman, J. Thomas, D.Q. Hwang, G.D. Conway, A. Hirose, F. Martin, P. Gierszewski
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Darlington NGS Unit 2 Fuel Damage Investigation

W.B. Stewart
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Development of a Strategic Plan for Performing Analysis in Support of an Operating Station: A PLGS Perspective

P.D. Thompson, D.F. Weeks, S. Alikhan
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The Experimental Program

G.J. Field
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Numerical Simulation of the Waterhammer Equations Using the Method of Characteristics and Comparison Against Experiments

Ajit P. Muzumdar
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Darlington Unit #2 Return to Service Program

W. Robbins, D.J. Benton
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Approach for the Management of Plant Aging

J.H.K. Lau, M. Tayal, E Nadeau, M.J. Pettigrew, I.E. Oldaker, W. Teper, Be Wong, F. Iglesias
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Development of Rush Rolled Joints for Bruce NGS A LSFCR Program

W.M.C. Knowles, T.A. Andreeff, C.W. Gordon, C.I. Jobe
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In-Process Control of Welding During CANDU Reactor Maintenance Operations

S. Venkatapathi, G.D. Moan, D.R. Brown, D.I. Hunter
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A New Fuel Channel for Bruce NGS 'A'

D.R. Brown
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Fuel Channel Installation Tooling for Retubing Brace Reactors

R.J. Gunn
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Dividing Steam-Water Annular Flow in T-Junctions with Horizontal Inlet and Downwardly Inclined Branch

F. Peng, M. Shoukri, A.M.C. Chan
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An Empirical Two-Fluid Model for Critical Flows

W.S. Liu
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A New Model for Void Fraction in Subcooled Boiling

H. Tang
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On the Modelling of Leak Rates Through Cracks in Pipes and Tubes

S.I. Osamusali, KO Crentsil, R.Y. Chu, J.C. Luxat
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An Experimental Study of Critical Heat Flux for Low Flow of Water in Vertical Round Tubes Under Low Pressure

Won-Pil Baek, Jae Wook Park, Soon Heung Chang
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Seismic Optimisation Approach for CANDU Modules

R.A. Ricciuti, A. Alizadeh, H. Jaikaran
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SLARette Mark 2 System

D.J. Burnett
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Control of CANDU-3 Fuel Handling Operations Using a Dedicated Distributed Control System

D. Arapakota, J.A. Yip, R. Anderson
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Systems View of CANDU Reactor Retubing

M. Macit Cobanoglu
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CANDU-3 Systematic Plant Review - A New Approach

R.K. Jaitly, P.J. Allen
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Derivation of Component Failure Data and Trend Analysis at Point Lepreau Generating Station

D.S. Mullin, T.E. Schaubel
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Pressure Oscillations in Darlington NGS Primary Heat Transport System Due to Tripping of One Main Circulating Pump

D.G. Meranda, A. Despotovic, V. Hera, J. Rubin
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Computer Code Verifications for PHT Purification System

F.Y.L. Su, H. Goulding
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Integrating CATHENA with CANDU Plant Controllers

D.J. Richards, R. Girard
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Thermalhydraulic Transient Analyses of the SGECS Initial Injection Period

B.S. Phillips, J.Y. Stambolich
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Simulation of the Combustion Chamber of an H2-O2 Thermal Recombiner

F. Fineschi, M. Bazzichi, G. Gardano
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Thermalhydraulic and Thermal Analysis Methodology of the CANDU-3 Reactor Endshield for a Loss of Flow Event

T.K. De, W.M. Collins
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Assessment of Shutdown System Trip Parameter Effectiv- of CANDU Rawtars Following In-core Loss of Coolant Accidents

A.F. Oliva, L.J. Watt
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Bruce NGS: Assessment of Calandria Tube btegtity Fallowing a Sudden Ptessupe Tube Failure

P.S. Kundurpi, A.P. Muzumdar, F.B.P. Tran
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New Flur Detectors for CANDU 6 Reactors

J.M. Cuttler, N. Medak
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Simulation of a CANDU Reactor Using a Rcal-Time Advanced Reilctor Core Model

Hoang Tran-Duc, Christian Paquette
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Development of an Outage Heat Sink Program for Bruce NGS A

R.J. Cox, W.K.G. Palmer
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CATHENA Validation Against MAPLE Subcooled Boiling Data

T.Y. Tran, S.Y. Shim, J.E. KowaIski, M. Salcudean
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Pre-test Simulations of the CHAN 28-Element High-Temperature Thermal-Chemical Experiment Using the Computer Codes CATHENA and CHAN-II-WL

Q.M. Lei, D.B. Sanderson, H.E. Rosinger
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Simulations of Molten Zircaloy/Pressure Tube Contact Experiments Using Computer Codes WALL25 and MINI-SMARTT-11

M.H. Choi, M. Bayoumi, P.S. Kundurpi
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Experimental and Theoretical Investigation of Pressure Tube Circumferential Temperature Gradients During Slow Coolant Boil-Off

Q.M. Lei, D.B. Sanderson, H.E. Rosinger
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Further Simulation of the Pressure Tube Circumferential Temperature Distribution Experiments (Make-up Water Experiments)

M. Bayoumi, W.C. Muir, P.S. Kundurpi
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Theoretical Prediction of the Garter Spring Positions Along the Channels of Some CANDU Reactors

Carlos H. Borzi
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Bearing-Pad/Pressure-Tube Rupture Experiments

R.G. Moyer, D.B. Sanderson, R.W. Tiede, H.E. Rosinger
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Ontario Hydro's Program for Enviromental Qualification of In-Service Plants

J.A. Blasko, R.P. Lindsay
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Procurement Strategy for Environmentally Qualified Materials

W. Seidl, P.V. Castaldo, D.B. Smith
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Service Qualification: The Impact of Human Performance Requirements

G.V. Burston, N. Garr
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Non-Linear Dynamic Analysis of Pipe Whip

M. Attab, S. Baset, W. Ajam
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Structural Design of Large Vertical Spent Fuel Dry Storage Module

W. Ajam, A. Khan, A. Alizadeh, H. Tran, B. Canas Calderon
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Application of Risk-Based Value-Impact Analysis in a Nuclear Regulatory Environment

Keith Dinnie, Ronald Land, Mark Stella
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A Framework for Defining the Functional Role of Annunciation

K.Q. Guo, E.C. Davey, S.A. Russomanno, J.R.P. Popovic, P. Archer
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Onset of Channel Flow Reversal in RD- l4M Natural Circulation Tests

P.T. Wan, W.I. Midvidy, J.C. Luxat
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Analysis of RD-14M Two-Phase Thermosyphoning Experiments and Associated CATHENA Simulation Results

P. Gulshani, D. Mori, J.N. Barkman, H. Huynh, P.D. Thompson
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Use of a Relational Database to Manage Information from Thermalhydraulic Experiments

R.S. Swartz, John C. Luxat, W.I. Midvidy, D.J. Richards
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Radiotherapy Compensators for an Unspecified Target Dose

Alexander Djordjevich
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Neutron Dosimetry and Spectroscopy Using Bubble Detectors and An Anthropomorphic Phantom

Hugues W. Bonin, Guy Desnoyers, Thomas Cousins
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Point Lepreau's LAN Based Station Control Computer and Generic Monitoring System

Harry Storey, B.K. Patterson, David Francis
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An Overview of the Metallurgical Investigation into the Failure of Darlington NGS Unit 2 Fuel Bundle End Plates

E.G. Price
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Darlington N 12 Event Investigation: Unit 1 & 2 Fuel and Fuel Channel Inspections

P.T. Truant, G.J. Field
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Dating the Fractures in Darlington Endplates from Oxide Thickness Measurements

V.F. Urbanic, M.A. Maguire, N. Ramasubramanian
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Development of Fatigue Failure Criteria for Darlington Fuel Bundle End Plates

Michael Gabbani, Tim Richards, A.M. Babayan, E.G. Price
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Fuel Testing to Simulate Darlington Channel and Fuel Damage

E.T.C. Ho, G.K. Shek, M.L. Vanderglas, M. Leger
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Towards a New Regulatory Regime for Operator Certification

E. Kohn, G. Hadaller
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XTEND - A Micro-Simulator for Use as a Training Aid in Trip Parameter Assessment

R. Thomas
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A Fuel Cooling Basis for Critical Safety Parameter Training

P.B. Middleton, T.A. Daniels, L.J. Watt
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Assessment of Training Effectiveness - A Trainer's Perspective

D.B. Reeves, D.L. Stafford, J.J. McCarthy, S. Turner
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Technical Requirements for Simulator-Based Testing of Candidates for Authorization

G.T. Bereznai, R.S. Bums, G.A. Hancock
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Competency Assessment of Reactor Operator Candidates Using Pull-Scope Simulators - The Emerging Canadian Approach

Gilles Turcotte, Andre Vachon
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Mechanical Maintenance Training Program

T.R. Simpson, A.M. McPartland, D.A. Weeks, R.M. Crawford, S.P. Turner
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