Forward Implementation of Nuclear Power Plant in a Developing Country - The Case of Turkey
N. Aybers (Turkish Atomic Energy Authority)
A1: Design & General Information
Overcoming the Fear of Radiation: The Key to the Golden Age of Nuclear Technology
J.M Cutler (AECL)
Increasing Operational Effectiveness and Reducing Licensing Risk of Design Changes to Nuclear Power Plants
M.P Feher, E.C. Davey (AECL), M. Tullet, C. McIntyre (OH)
Staff Training Program of CANDU Projects in Saskatoon
J. Huterer (AECL)
The Evolution of CANDU 6 Design
J.M. Hopwood, P.J. Allen, A.R. McKenzie (AECL)
Preparation for the Future: The Implications of the Information Revolution for the Canadian Nuclear Industry
M.O. Luke (AECL)
A2: Waste Management & the Environment
Experience of the Low-Level Radioactive Waste Management Office with EARP
B.J. Franklin, R.W. Pollock (AECL)
Socio-Economic Impacts Between the Nuclear Industry and Aboriginal People
D.G. Malcolm (Aurora College)
Estimation of Nuclide Transfer and Dose in Non-Human Species: Application of Risk Assessment Techniques
R.C. Macdonald (AECL)
Integral Solution of Equiaxed Solidification with an Interface Kinetics Model for Nuclear Waste Management
G.F. Naterer (UNB)
A3: Instrumentation & Control I
CANDU 9 Control Center Mockup
A. Webster, M. MacBeth (AECL)
Distributed Control System for CANDU 9 Nuclear Power Plant
J.E. Harber, M.K. Kattan, M.J. MacBeth (AECL)
Advanced Control Center Information System (ACCIS)
W.Fieguth, J. Hinton, K. Stephens (AECL)
Canadian CANDU Plant Historical Data Systems: A Review and Look to the Future
M. DeVerno, J. de Grosbois, H. Pothier, C. Xian, M. Bosnich, J. Hinton, G. Gilks (AECL)
A4: Safety Analysis I
Validation of Computer Codes used in Safety Analyses of CANDU Power Plants
E.O.Moeck (AECL), J.C. Luxat (OH), L.A. Simpson (AECL), M.A. Petrilli (HQ), P.D. Thompson (NBP)
Calculation of Instrument Loop Errors in Special Safety Systems of CANDU Reactors. A Statistical Approach
S. Russomanno (AECL), S.Basu (OH), D. Rennick (CANTECH Intl)
Monitoring the Risk of Loss of Heat Sinks During Plant Shutdowns at Bruce Generating Station "A"
K. Krishnan, D. Mancuso, D. Vecchiarelli (OH)
A Bayesian Reliability Study on Motorized Valves for the Emergency Core Cooling, Heat Transport Isolation and Shutdown Cooling Systems at Gentilly-2 Nuclear Generating Station
J.E. Smith, D.F. Rennick, A. Nainer (CANTECH Intl), M. Demers, R. Vaillancourt (HQ)
Fuel Bundle Impact Velocities due to Reverse Flow
N.N. Wahba, K.E. Locke (OH)
The Seismic Fragility Analysis for Multi-Story Steel Structure in CANDU Nuclear Power Plant
K.H. Hwang, B.S. Lee, S-K Kang (KOPEC), W.H. Tong (EQE International), S.R. Roh (KEPRI)
B1: Reactor Physics
On-Line Power Monitoring in CANDU using PMFD
J. Pitre, P.S.W. Chan (AECL)
In-Reactor Test to Assess Alternate Scheme for Adjuster Rod Banking of the CANDU-6 Reactor
J.A Walsworth (ANSL), C.N. Newman (NBP)
Performance of the Regional Overpower Protection Trip System during Reactor Shutdown and Restart Conditions
J.A Walsworth (ANSL), W.J. Harmann (AECL), E.G. Young (NBP)
Modeling of CANDU Reactivity Devices with WIMS-AECL/MULTICELL and Superhomogenization
J.V. Donnelly (AECL), B.J. Min (KAERI), E.V. Carruthers, K. Tsang (AECL)
LEU-Fueled Slowpoke-2 Modeling with MCNP4A
J.M.R. Pierre, H.W.J. Bonin (CMRC/RMCC)
A Multi-Point Kinetics Model Applied to Three-Dimensional Neutronic Transient Analysis
H.D. Kirn, K.S. Park (Korea Inst for Advanced Engineering)
B2: Instrumentation & Control II
Hardware Replacements and Software Tools for Digital Control Computers
R.A.P. Walker, B-C Wang, J. Fung (AECL)
Development of DCC Software Dynamic Test Facility
A.M. MacDonald, N.D.Thai, W.J. Buijs, B.C. Wang, C.R.A. Burgis (AECL)
Comparison of Multivariate and Univariate Statistical Process Control and Monitoring Methods
R. P. Leger, W.J. Garland, J.F. MacGregor, W.F.S. Poehlman (MacU)
Use of Wavelet Transform for Signal Denoising of Nuclear Power Plant Data
J.M. Lina, H. Dai, W. Thompson (ANSL), B. Goulard (UdM)
Reactor Coolant Flow Measurements at Point Lepreau
J. Brenciaglia, Y. Gurevich, G. Liu, A. Lopez (AMAG), W. Hartmann (AECL), P.D. Thompson (NBP), D. Zobin (OH)
B3; Thermalhydraulics I
Comparison of CATHENA against Stern 37-Element CHF Tests
G. Sabourin, et al. (AECL)
Simulation of Refill Tests for a CANDU-Type End-Fitting
E.L. Bibeau, M.E. Lavack (AECL)
A Simulation of a Hypothetical Stuck Open LRV at PLGS
R. Girard (NBP)
Commissioning of CATHENA/LEPCON to Simulate Plant Transmitters at PLGS
M. Cormier (UNB), A. Galia, R. Girard (NBP)
Use of Operational Data for the Validation of the SOPHT Thermal-Hydraulic Code
L. Shoukas, G. Martin, S.F. Ho, Z. Siddiqui, B. Phillips (OH)
Numerical Model of CANDU Fuel Channels Using the SIMPLEC Method
G.F. Naterer (UNB)
B4: Safety Analysis II
MODTURC_CLAS Analysis of Moderator Poison/Coolant Mixing in the Calandria due to a Pressure Tube/Calandria Tube Rupture during an Overpoisoned Guaranteed Shutdown State
J.C. MacKinnion, J.K. Szymanski, G. Balog (OH)
Reducing Uncertainties in Moderator Sub-Cooling Assessments - Activities Underway at PLGS
W.J. Thompson (ANSL), F.R. Steward (UNB)
A Model for Turbine Hall Pressure Relief Panel
M.S. Quraishi (Sadiq Yousuf Group), R.A. Gibb (NBP)
Prediction of Fan Assisted Flow in a Duct/Pipe Network
M.S. Quraishi (Sadiq Yousuf Group)
Modeling of Condensation or Evaporation Transients in the Piteus and Phebus FP Containment Vessels
P.B. Spitz (Institut de Protection et de Sûreté Nucléaire), S. Tirini (ENEA, Italy)
Using Microgravity Conditions to Measure Aerosol Physics Parameters for Containment Analysis
C.K. Scott, M. Abdelbaky (ANSL)
C1: In-Core Instrumentation
Comparison of Measured and Predicted Sensitivities of In-Core Flux Detectors
D.P. McAllindon (AECL)
Degradation and Life Expectancy Test for Various BF3 Detectors
T. Qian, N. Keller, P. Tonner (AECL)
Investigation of EMI Effect of Arc Welding on Startup Instrumentation
T. Qian, W. Kalechstein (AECL), D. Cosgrove, U. Mondal (OH)
Practical Test Set-Up and Method for Determining the Response Characteristics of a Log Rate over 6 Decades
J. Kemp (IST Canada)
Noise Analysis Based Validation of the Dynamics of In-Core Flux Detectors and Ion-Chambers used in SDSs and RRS Systems
O. Glöckler, D. Cooke, M.V. Tulett (OH), D.P. McAllindon (AECL)
C2: High Temperature Fuel & Fuel Channels I
Approaches to Simulate Channel and Fuel Behavior using CATHENA and ELOCA
G. Sabourin (AECL), H. Huynh (HQ)
The Fuel and Channel Thermal/Mechanical Behavior Code FACTAR: Version 2.0 for Loss of Emergency Coolant Injection Simulations
C.J. Westbye, J.C. MacKinnon, B.W. Gu (OH), J.D. Ballyck (AECL), A.C. Brito, D. Evens, R.C.K. Rock (OH)
A Model to Calculate Oxidation of UO2 in Steam Environments for Implementation in the Fuel and Channel Thermal/Mechanical Behavior Code FACTAR
A.C. Brito, F.C. Iglesias, Y. Liu, C.J. Westbye (OH), D.S. Cox (AECL), B.J. Lewis (CMRC/RMCC)
Likelihood and Consequences of Fuel String Compression at Point Lepreau Generating Station
P.J. Reid (ALARA), R.A. Gibb (NBP)
A Modal Method for Transient Thermal Analysis of CANDU Fuel Channel
J-W Park IAE Korea), A.P. Muzumdar (AECL)
Recent Improvements in Modelling Fuel Behaviour during Normal Operating Conditions; Incremental Pellet-Deformation Model
V.I. Arimescu (AECL)
C3: Plant Operations I
SEBIM Pilot Operated Tandems: A New Solution for Darlington NGS Bleed Condenser Relief Valves
H. Paetzold, V. Hera (OH), G. Schaumburg (Group SEBIM), S. Masala (Spectrum Engineering)
Hand-held Electronic Procedure Environment
E. Kennedy, K. Doniz (AECL)
PLGS-1995 SLAR Program
R. Baker (NBP)
Heat Sink Considerations During SLAR Defuelling Activities of the 1995 Maintenance Outage at the Point Lepreau G.S.
R.A. Richard (ANSL), D.J. Edgar (Systec), R.A. Gibb (NBP)
Element Bow Profiles from New and Irradiated CANDU Fuel Bundles
D. Dennier, A.M. Manzer, M.A. Ryz (AECL), E. Kohn (OH)
The Advanced Carrier Bundle to Irradiate Materials Samples in CANDU Power Reactors
P. Alavi, I.E. Oldaker, A.L. Celovsky (AECL)
C4: Thermalhydraulics II
Development Status of the Code TUF
W.S. Liu, A. Tahir, E. Zaltsgendler, W. Kelly, R.K. Leung (OH)
Investigation of Flow Blockage in a Fuel Channel with the ASSERT Subchannel Code
G.D. Harvel, R. Dam, M. Soulard (AECL), R.A. Gibb (NBP)
A Numerical Investigation of Coolant Thermal Mixing within 28-Element CANDU Fuel Bundles using ASSERT-PV
M.F. Lightstone (UT), R. Rock (OH)
Numerical Model of CANDU Fuel Channels Using the SIMPLEC Method
G.F. Naterer (UNB)
D1: Safety Analysis III & Environmental Qualification
Equipment Qualification Testing - A Practical Approach
G.A. Davies, R.I. McDougall, M.P. Poirier, R.J. Horton (Mu-Sigma Consulting Engineers and Laboratories)
Condition Monitoring of Nuclear Cable using the Indenter Modulus
M.P. Poirier (Mu-Sigma Consulting Engineers and Laboratories), D.J. Stonkus (DJS Associates), S. Benson (NBP)
LOCA Power Pulse Analysis for CANDU-6 CANFLEX Core
J.H. Choi, M.Y. Ohn, C.J. Bae, B.K. Kim, H.C. Suk (KAERI)
Effect of Fuel String Relocation on the Consequences of Postulated Inlet Header LBLOCA in KANUPP Reactor
I. Ahmed (KANUPP), H.C. Chow, M.H. Younis (AECL), N.T. Le (OH)
Verification of the Point Lepreau SMOKIN Code with Plant Transient Data
R.C. Robinson, W. Thompson, A. Ozdemir (ANSL), E. Young, C. Newman (NBP)
Timing of Core Damage States Following Severe Accidents for the CANDU Reactor Design
N.N. Wahba (OH), Y.T. Kim (AECL), P.M. Petherick, S.G. Lie (OH)
Failure Mode and Effect Analysis: Experimental Reliability Determination for the CANDU Reactor Equipments
G. Vieru (Inst for Nuclear Research, Romania)
D2: Plant Operations II
Gentilly-2 and Point Lepreau Divider Plate Replacement
W. Schneider, G. McClellan, S. Weston, E. Kiisel, C. Holmes (BW), J. Forest (HQ), K. Verma (NBP)
Steam Generators Secondary Side Chemical Cleaning at Point Lepreau using the Siemen's High Temperature Process
K. Verma, C. MacNeil (NBP), S. Odar, K. Kuhnke (Siemens/KWU)
Steam Generator Primary Side Tube Cleaning at Point Lepreau using the Siemen's Mechanical Cleaning Process
K. Verma (NBP), S. Odar (Siemens/KWU), D. Scott (AECL)
Consequences of Foreign Materials Being Left in the PHTS at Point Lepreau
S. Groom (NBP)
Channel Coolant Flow Verification Support for the December 1995 Startup at the Point Lepreau Generating Station using NUCmC MOD 1.911 and Pre-outage Channel Flow Models
W.J. Hartmann (AECL), P.D. Thompson (NBP), M.R. Soulard (AECL)
Assessment of the Integrity of KANUPP Fuel Channels
B.A. Cheadle, A. Celovsky (AECL), M. Ghafoor, W. Butt (KANUPP)
D3: High Temperature Fuel & Fuel Channels II
Total Emissivity of CANDU Fuel Sheath at High Temperatures
P.M. Mathew, I.M. George (AECL)
The Analysis of Bearing-Pad to Pressure-Tube Contact Heat Transfer Experiments
T. Nitheanandan, Q.M. Lei, R.G. Moyer (AECL)
Simulation and Analysis of Bearing Pad to Pressure Tube Contact Heat Transfer under Large Break LOCA Conditions
M.H. Bayoumi, W.C. Muir, P.B. Middleton (OH)
Experimental Investigation of Thermal Behavior of Concentric Tubes During a Severe Accident
K. Kumasaka (Hitachi), R.J. Hammersley, R.E. Henry (Fauske & Associates), K. Mizuno (Hitachi)
Effects of Neutron Irradiation on Mechanical Properties of Heat Treated Zr-2.5Nb Pressure Tube in Prototype Advanced Thermal Reactor FUGEN
K. Ohara, Y. Abe, S. Ukai, M.H. Koike (Power Reactor and Nuclear Development Corporation, Japan)
E1: Design & Radiation Biology
A Passive Emergency Heat Sink for Water-Cooled Reactors with Particular Application to CANDU
N.J. Spinks (AECL)
Using Range Vision for Telerobotic Control in Hazardous Environments
M.G. Lipsett (AECL), M. Greenspan (NRCC), W.J. Ballantyne (Spar Aerospace)
Antioxidants and Biological Radiation Protection
C.L. Greenstock, K.J. Lenton (AECL)
RBE of Tritium Measured in Human Cells Using Cytogenetic Endpoints
K.L. Gale, B.P. Smith, D.P. Morrison, N.E. Gentner (AECL)
E2: Thermalhydraulics III
Shutdown Cooling Temperature Perturbation Test for Analysis of Potential Flow Blockages
J. Handbury (ANSL), C. Newman, T. Whynot, E. Young (NBP)
Assessment of Fuel Cooling under Natural Circulation Conditions in Intact Loop for LOCA Scenarios in Gentilly-2
P. Gulshani (AECL), H. Huynh (HQ)
Determination of Representative CANDU Feeder Dimensions for Engineering Simulator
S. Cho, A.P. Muzumdar (Korea IAE)
E3: Research Facilities, Fundamental Research & Fusion
Progress in Developing the Concept for the Irradiation Research Facility
A.G. Lee, W.E. Bishop, G.E. Gillespie, Y. Zeng (AECL)
Cold Neutron Source (CNS) Facility in HANARO Reactor
C.O. Choi, M.S. Cho, S.H. Park, K.N. Park (KAERI)
Measurement of Tritium on Surfaces
N.P. Kherani, W.T. Shmayda (OH)
Multielemental Neutron Activation Analysis of some Egyptian Cement Samples
E.A. Eissa, N.B. Rofail, A.M Hassan (RNPD-AEA), N. Abdel-Basset, A. Sroor (Ain Shams)
Analysis of Tritium Kinetics of Sibelius Beryllium
S. Cho (Korea IAE)
Effect of LiOT on Tritium Inventory of Li2 Solid Breeder
S. Cho (Korea IAE)
E4: Plant Operations III
Detection of Gaseous Heavy Water Leakage Points in CANDU-6 Pressurized Heavy Water Reactors
T-K Park, S-H Jung (KAERI)
Header/Feeder Cleaning & Maintenance
S. Weston (BW)
Transient Behaviour of Desolved Hydrogen and Oxygen in the Primary Heat Transport System during the 1995 Start-Up period at PLGS
L.T. Yang (CNER), C. McNeil, D. Loughead (NBP)
Assessment of Heat Sink Capabilities without Forced Circulation at Very Low Decay Powers
D.J. Edgar (Systec)
