Published: 1996-06-09

Articles

Overcoming the Fear of Radiation: The Key to the Golden Age of Nuclear Technology

J.M. Cutler
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Increasing Operational Effectiveness and Reducing Licensing Risk of Design Changes to Nuclear Power Plants

M.P. Feher, E.C. Davey, M. Tullet, C. McIntyre
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Staff Training Program of CANDU Projects in Saskatoon

J. Huterer
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The Evolution of CANDU 6 Design

Jerry M. Hopwood, P.J. Allen, A.R. McKenzie
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Preparation for the Future: The Implications of the Information Revolution for the Canadian Nuclear Industry

Michael O. Luke
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Experience of the Low-Level Radioactive Waste Management Office with EARP

B.J. Franklin, R.W. Pollock
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Socio-Economic Impacts Between the Nuclear Industry and Aboriginal People

David G. Malcolm
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Estimation of Nuclide Transfer and Dose in Non-Human Species: Application of Risk Assessment Techniques

R.C. Macdonald
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Integral Solution of Equiaxed Solidification with an Interface Kinetics Model for Nuclear Waste Management

G.F. Naterer
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CANDU 9 Control Center Mockup

A. Webster, M. MacBeth
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Distributed Control System for CANDU 9 Nuclear Power Plant

J.E. Harber, M.K. Kattan, M.J. MacBeth
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Advanced Control Center Information System (ACCIS)

W. Fieguth, J. Hinton, K. Stephens
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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
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Validation of Computer Codes used in Safety Analyses of CANDU Power Plants

E.O. Moeck, J.C. Luxat, L.A. Simpson, M.A. Petrilli, P.D. Thompson
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Calculation of Instrument Loop Errors in Special Safety Systems of CANDU Reactors: A Statistical Approach

S. Russomanno, S. Basu
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Monitoring the Risk of Loss of Heat Sinks During Plant Shutdowns at Bruce Generating Station A

K.S. Krishnan, F. Mancuso, D. Vecchiarelli
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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

James Smith, Donald F. Rennick, Alina Nainer, Michel Demers, Raynald Vaillancourt
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Fuel Bundle Impact Velocities due to Reverse Flow

N.N. Wahba, K.E. Locke
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The Seismic Fragility Analysis for Multi-Story Steel Structure in CANDU Nuclear Power Plant

Kyu Ho Hwang, Beam-Su Lee, Sun-Koo Kang, Seong Roh Roh
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On-Line Power Monitoring in CANDU using PMFD

J. Pitre, P.S.W. Chan
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In-Reactor Test to Assess Alternate Scheme for Adjuster Rod Banking of the CANDU-6 Reactor

J.A. Walsworth, C.N. Newman
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Performance of the Regional Overpower Protection Trip System during Reactor Shutdown and Restart Conditions

J.A. Walsworth, W.J. Hartmann, E.G. Young
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Modeling of CANDU Reactivity Devices with WIMS-AECL/Multicell and Superhomogenization

James V. Donnelly
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LEU-Fueled Slowpoke-2 Modeling with MCNP4A

J.M.R. Pierre, H.W.J. Bonin
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A Multi-Point Kinetics Model Applied to Three-Dimensional Neutronic Transient Analysis

H.D. Kim, K.S. Park
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Hardware Replacements and Software Tools for Digital Control Computers

R.A.P. Walker, B.C. Wang, J. Fung
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Development of DCC Software Dynamic Test Facility

A.M. McDonald, N.D. Thai, W.J. Buijs, B.C. Wang, C.R.A. Burgis
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Comparison of Multivariate and Univariate Statistical Process Control and Monitoring Methods

R.P. Leger, Wm. Garland, J.F. MacGregor, W.F.S. Poehlman
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Use of Wavelet Transform for Signal Denoising of Nuclear Power Plant Data

J.-M. Lina, H. Dai, W. Thompson, B. Goulard
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Comparison of CATHENA against Stern 37-Element CHF Tests

G. Sabourin
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Simulation of Refill Tests for a CANDU-Type End-Fitting

E.L. Bibeau, M.E. Lavack
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A Simulation of a Hypothetical Stuck Open LRV at PLGS

R. Girard
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Reactor Coolant Flow Measurements at Point Lepreau

G. Brenciaglia, Y. Gurevich, G. Liu, A. Lopez, W. Hartmann, P. Thompson, D. Zobin
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Commissioning of CATHENA/LEPCON to Simulate Plant Transmiters at PLGS

M. Cormier, A. Galia, R. Girard
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Use of Operational Data for the Validation of the SOPHT Thermal-Hydraulic Code

L. Shoukas, G. Martin, S.F. Ho, Z. Siddiqui, B. Phillips
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Numerical Model of CANDU Fuel Channels Using the SIMPLEC Method

G.F. Naterer
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Reducing Unceratinties in Moderator Sub-Cooling Assessments - Activities Underway at PLGS

W.J. Thompson, F.R. Steward
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A Model for Turbine Hall Pressure Relief Panel

M.S. Quraishi, R.A. Gibb
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Prediction of Fan Assisted Flow in a Duct/Pipe Network

M.S. Quraishi
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Modeling of Condensation or Evaporation Transients in the PHEAS and PHEBUS FP Containment Vessels

Patrick B. Spitz, Sandro Tirini
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Comparison of Measured and Predicted Sensitivities of In-Core Flux Detectors

D.P. McAllindon
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Degradation and Life Expectancy Test for Various BF3 Detectors

T. Qian, N. Keller, P. Tonner
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Investigation of EMI Effect of Arc Welding on Startup Instrumentation

T. Qian, W. Kalechstein, D. Cosgrove, U. Mondal
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Practical Test Set-Up and Method for Determining the Response Characteristics of a Log Rate over 6 Decades

John Kemp
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Noise Analysis Based Validation of the Dynamics of In-Core Flux Detectors and Ion-Chambers used in SDSs and RRS Systems

O. Glockler, D. Cooke, M.V. Tulett, D.P. McAllindon
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Approaches to Simulate Channel and Fuel Behavior using CATHENA and ELOCA

G. Sabourin, H.M. Huynh
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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, J.D. Ballyk, A.C. Brito, D. Evens, R.C.K. Rock
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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, D.S. Cox, Brent J. Lewis
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Likelihood and Consequences of Fuel String Compression at Point Lepreau Generating Station

P.J. Reid, R.A. Gibb
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A Modal Method for Transient Thermal Analysis of CANDU Fuel Channel

Jong-Wook Park, A. Muzumdar
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Recent Improvements in Modelling Fuel Behaviour during Normal Operating Conditions: Incremental Pellet-Deformation Model

V.I. Arimescu
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SEBIM Pilot Operated Tandems: A New Solution for Darlington NGS Bleed Condenser Relief Valves

H. Paetzold
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Hand-held Electronic Procedure Environment

Evan Kennedy, Karen Doniz
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PLGS-1995 SLAR Program

Ray Baker
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Heat Sink Considerations During SLAR Defuelling Activates of the 1995 Maintenance Outage at the Point Lepreau G.S.

R.A. Richard, D.I. Edgar, R.A. Gibb
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Element Bow Profiles from New and Irradiated CANDU Fuel Bundles

D. Dennier, A.M. Mazner, M.A. Ryz, E. Kohn
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The Advanced Carrier Bundle to Irradiate Materials Samples in CANDU Power Reactors

P. Alavi, I.E. Oldaker, A.L. Celovsky
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Development Status of the Code TUF

W.S. Liu, A. Tahir, E. Zaltsgendler, W. Kelly, R.K. Leung
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Investigation of Flow Blockage in a Fuel Channel with the ASSERT Subchannel Code

G.D. Harvel, R. Dam, M. Soulard, R.A. Gibb
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A Numerical Investigation of Coolant Thermal Mixing within 28-Element CANDU Fuel Bundles using ASSERT-PV

M.F. Lightstone, R. Rock
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Equipment Qualification Testing - A Practical Approach

G.A. Davies, R.I. McDougall, M.P. Poirier, R.J. Horton
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Condition Monitoring of Nuclear Cable using the Indenter Modulus

M. Poirier, D.J. Stonkus, S. Benson
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LOCA Power Pulse Analysis for CANDU-6 CANFLEX Core

J.H. Choi, M.Y. Ohn, C.J. Bae, B.K. Kim, Ho Chun Suk
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Effect of Fuel String Relocation on the Consequences of Postulated Inlet Header LBLOCA in KANUPP Reactor

Iqbal Ahmed, Hank Chow, Mohamed Younis, Nga Le
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Verification of the Point Lepreau SMOKIN Code with Plant Transient Data

R. Robinson
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Timing of Core Damage States Following Severe Accidents for the CANDU Reactor Design

N.N. Wahba, Y.T. Kim, P.M. Petherick, S.G. Lie
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Gentilly-2 and Point Lepreau Divider Plate Replacement

W. Schneider, G. McClellan, S. Weston, E. Kiisel, C. Holmes, J. Forest, K. Verma
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Steam Generators Secondary Side Chemical Cleaning at Point Lepreau using the Siemen's High Temperature Process

Karnal Venna, Cynl MacNeil, Suat Odar, Klaus Kuhnke
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Steam Generator Primary Side Tube Cleaning at Point Lepreau using the Siemen's Mechanical Cleaning Process

Kamal Verma, Suart Odar, David Scott
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Consequences of Foreign Materials being left in the PHTS at Point Lepreau

S. Groom
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Channel Coolant Flow Verification Support for the December 1995 Startup at the Point Lepreau Generating Station using NUCIRC MOD 1.911 and Pre-outage Channel Flow Models

W.J. Hartmann, P.D. Thompson, M.R. Soulard
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Assessment of the Integrity of KANUPP Fuel Channels

B.A. Cheadle, A. Celovsky, M. Ghafoor, W. Butt
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Gentilly-2 and Point Lepreau Divider Plate Replacement

W. Schneider, G. McClellan, S. Weston, E. Kiisel, C. Holmes, J. Forest, K. Verma
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Total Emissivity of CANDU Fuel Sheath at High Temperatures

P.M. Mathew, I.M. George
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Fuel Channel Thermal-Chemical Experiment CS28-3

P.J. Mills, D.B. Sanderson, K.A. Haugen, G.G. Haacke
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The Analysis of Bearing-Pad to Pressure-Tube Contact Heat Transfer Experiments

Thambiayah Nitheanandan, Q.M. Lei, R.G. Moyer
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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
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Experimental Investigation of Thermal Behavior of Concentric Tubes During a Severe Accident

K. Kumasaka, R.J. Hammersley, R.E. Henry, K. Mizuno
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Effects of Neutron Irradiation on Mechanical Properties of Heat Trested Zr-2.5Nb Pressure Tube in Prototype Advanced Thermal Reactor FUGEN

K. Ohara, Y. Abe, S. Ukai, M.H. Koike
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A Passive Emergency Heat Sink for Water-Cooled Reactors with Particular Application to CANDU

N.J. Spinks
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Using Range Vision for Telerobotic Control in Hazardous Environments

M.G. Lipsett, M. Greenspan, W.J. Ballantyne
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Factors that Affect Radiation Risk

D.R. Boreham, D.P. Morrison, R.E.J. Mitchel
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Antioxidants and Biological Radiation Protection

C.L. Greenstock, K.J. Linton
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RBE of Tritium Measured in Human Cells Using Cytogenetic Endpoints

K.L. Gale, B.P. Smith, D.P. Morrison, N.E. Gentner
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Shutdown Cooling Temperature Perturbation Test for Analysis of Potnetial Flow Blockages

J. Handbury, C. Newman, T. Whynot, E. Young
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Assessment of Fuel Cooling under Natural Circulation Conditions in Intact Loop for LOCA Scenarios in Gentilly-2

P. Gulshani, H.M. Huynh
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Determination of Representative CANDU Feeder Dimensions for Engineering Simulator

Seungyon Cho, Ajit Muzumdar
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Progress in Developing the Concept for the Irradiation Research Facility

A.G. Lee, W.E. Bishop, G.E. Gillespie, Y. Zeng
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Cold Neutron Source (CNS) Facility in HANARO Reactor

Chang-oong Choi, Man Soon Cho, Sun Hee Park, Kook-Nam Park
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Measurement of Tritium on Surfaces

N.P. Kherani, W.T. Shmayda
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Multielemental Neutron Activation Analysis of some Egyptian Cement Samples

E.A. Eissa, N.B. Rofail, A.M. Hassan, N. Abdel-Basset, A. Sroor
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Analysis of Tritium Kinetics of Sibelius Beryllium

Seungyon Cho
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Effect of LiOT on Tritium Inventory of Li2O Solid Breeder

Seungyon Cho
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Detection of Gaseous Heavy Water Leakage Points in CANDU-6 Pressurised Heavy Water Reactors

Tae-Keun Park, Sung-Hoon Jung
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Header/Feeder Cleaning and Maintenance

S. Weston
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Transient Behaviour of Desolved Hydrogen and Oxygen in the Primary Heat Transport System during the 1995 Start-Up period at PLGS

L.T. Yang, C. McNeil, D. Loughead
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Assessment of Heat Sink Capabilities without Forced Circulation at Very Low Decay Powers

D.J. Edgar
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