Published: 1999-06-01

Articles

Determination of 17 Elements in 20 Canadian Mineral Waters by Evaporation and Systematic Instrumental Neutron Activation Analysis

Pham Van Duong, L. Zikovsky
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Inspection Surveys of X-Ray Inspection Systems: Results of Five Years and Implications on Future Management of Radiation Risks

HP Maharaj
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ChemAND-A System Health Monitor for Plant Chemistry

C.W. Turner, G.R. Mitchet, P.V. Balakrishnan, G. Tosello
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A Study on the Behavior of Debris around a Sump of a Safety Cooling System

Jin-Hyo Bae, Man Heung Park
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Nuclear Power and Carbon Dioxide Free Automobiles

Duane R. Pendergast
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Nuclear Energy in Industry: Application to Oil Production

John K. Donnelly, Duane R. Pendergast
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The Solution of Sparse Matrices in CATHENA

T.G. Beuthe, J.B. Hedley
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Application of the CATHENA Thermalhydraulics Code to MAPLE Research Reactor Safety Analysis

N.K. Popov, R. Kouyoumdjian, H. Sills, A.G. Lee, V. Langman
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Endshield Tubesheets Response to Impact Velocity due to Reverse Flow Resulting from Large LOCA

N.N. Wahba, J.K. Chan, M.H. Bayoumi
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CANDU 9 Large LOCA Uncertainty Analysis

Amad Adhul-Razzak, Maw-Rong Lin
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ASSERT-PV Simulations of Two-Phase Flow in Horizontal and Vertical Subchannels

J.W. Park, K.M. Chae, H. Choi
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Flow stability of liquid metal flow under transverse magnetic field

Hee Reyoung Kim, Ho-Yum Nam, Yong-Kyun Kim, Sang Hee Hong
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Evaluation of Supercell Methodologies Using ZED-2 Measurements

Benoit Arsenault, H.C. Chow
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Development of NDA Measurement Method to Determine the Fissile Material Contents for DUPIC Fuel

Hee Young Kang, Young-Gil Lee, Hong-Ryul Cha, Gil Mo Ku, Ho Dong Kim, Jong Sook Hong, Myung-Seung Yang
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MCNP Anaylsis of a D2O-Filled Fuel-Channel Penetration Through the End Shield

L. Kirilosky, K.T. Tsang
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Development of an Isotopic Depletion Method for Reactor Core Calculations

M. Boubcher, Guy Marleau, Daniel Rozon
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Development of Limiting Decay Heat Values

V.A. Khotylev, J.W. Thompson, R.A. Gibb
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Coherent Structures in the Gaps of Rod Bundles

M.S. Guellouz, S. Tavoularis
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Thermalhydraulic Characteristics of CANDU 9 Moderator System

Ji Zhang, Maw-Rong Lin
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Assessment of Fuel Cooling Under Shutdown Conditions in Gentilly 2

P. Gulshani, H.M. Huynh
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Effectiveness of the High Capacity Blowdown for Steam Generator Sludge Removal

S.J. Baik, D.M. Chung, T.S. Ro
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Measurement of the Dynamic Response of Differential Pressure Transmitters Using a Response Time Tester

H.W. Hinds
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Determining Prompt Fractions of In-Core Flux Detectors During Full-Power Operation in CANDU

B. Sur, P. Kumli, J.P. Johnston, P.D. Tonner
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The Measurement and Analysis of Dynamic Response of Alarm Units

H.W. Hinds
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Dynamic Response of the SDS Flow-Measurement System in CANDU

V.T. Koslowsky, H.W. Hinds, P.D. Tonner, O. Glockler
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Computing Channel RTD Systematic Errors Using Small Reactor Derates

V. Costiuc, J. Handbury, T. Whynot
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Commercial Aircrew Radiation Dosimetry using a Tissue Equivalent Proportional Counter

A.R. Green, Brent J. Lewis, L.G.I. Bennett, M. Pierre, T. Cousins
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Characterization of the Slug Formation in Counter-Current Two-Phase Flows

A. Teyssedou, N. Onder, H. Saygin, H. Huynh
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Prediction of the Flooding Point in a Vertical to Horizontal Tube with and without Obstructions

P. Tye, A. Teyssedou, A. Tapucu, W.I. Midvidy
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Application of Experience to the Design of the Steam Generators for the CANDU 9

James Smith
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On the Prediction of Fretting Wear of Heat Exchanger/Steam Generator Tubing

San Iyer
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Pressurizer Manway Closure Re-Engineering

R. Horvath, J. Tang, D. Joudrey, J. Millman, D. Pritchard
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Validation of WIMS-AECL/3DDT Code Package Using the IAEA 10 MW Benchmark Problem for the McMaster Nuclear Reactor Fuel Conversion Analysis

Hassan AlBasha
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Self-Collision Rebalancing Technique for the MCI Characteristics Solver

G.J. Wu, Robert Roy
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Generation of Microscopic Pseudo Fission-Products Properties

H. Benjaafar, Guy Marleau
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The Effect of PWR Fuel Management Strategy on DUPIC Fuel Cycle

Wei Shen, Daniel Rozon
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Experimental and Computational Determination of Radiation Dose Rates in the SLOWPOKE-2 Research Reactor at the Royal Military College of Canada

G.B. Lamarre, H.W. Bonin
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Development of Special Tools for the Cleaning of Reactor's Interior in HANARO

Yeong-Garp Cho, Jung-Hee Lee, Jeong-Soo Ryu, Jong-Sup Wu, Hoan-Sung Jung
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Significance of Beta and Gamma Dose on Environmental Qualification of Components

Kam Aydogdu, K.T. Tsang
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Point Lepreau Generating Station Strategic Planning Process Integrating Strategic Objectives into Operational Planning

Syd Turner
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The Unavailability and Delay Time of an Action due to the Drift of the Instruments

H. Tang
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CANFLEX Demonstration Irradiation at Point Lepreau: Background and Observations

R.A. Gibb, R.W. Sancton, P.J. Reid, Josephin Bullerwell
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Improvements to the Control Room Operator Workspace at Point Lepreau

Tom Hitchcock, H. Storey, Eric Davey, Bryan Patterson
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Control Room Monitoring of Process Conditions and Identification of Improvements to Darlington Monitoring Displays

Eric Davey, M. Tonello, D. Rivera
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Implementation of New Operations Standards at Darlington Nuclear Generating Station

Ron Chatterton
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Evaluating Nuclear Power Plant Crew Performance During Emergency Response Drills

Doron Rabin
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Psychological Error Mechanisms

Bryan Patterson, M. Bradley, L. Jeffery
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The Professional Development Culture and Performance Improvement

C.K. Scott
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MAPLE Research Reactor Safety Margins Uncertainty Assessment Methodology

H.E. Sills, R.B. Duffey, T.H. Andres
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Fission-Product Transport and Retention in the PHTS Under Accident Conditions

Lawrence Dickson, Raymond Dickson
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Computer Simulation of Aerosol Dynamics with a Unified Agglomeration Kernel

Yves Trudeau, Wen Chen, C. Scott, Kenneth Oxorn
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Implementation of Common Industry Safety Analysis Codes

John C. Luxat, V.G. Snell, M.A. Petrilli, P.D. Thompson
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Graphical Environmental Pathway Analysis Software TEDII-60 Incorporating ICRP-60 Recommendations

Sang-Ho Kang, Kyung-Hee Lee
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Regulatory Considerations of Lay-Up of Power Reactors

Patrick Hawley
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Comparison of MCNP48 and WIMS-AECL Calculations of Cooling-Void-Reactivity Effects for Uniform Lattices of CANDU Fuel

Kenneth Kozier
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Verification of Two-Group CERBERUS for a Loss-of-Coolant Analysis in a Simplified Reactor Model

James V. Donnelly, E.M. Nichita
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The Improved Quasistatic Method vs the Direct Method: A Case Study for CANDU Reactor Transients

Siamak Kaveh, Jean Koclas, Robert Roy
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Simulation of CANDU Reactor Transients Using Three Level Space Time Kinetics

Siamak Kaveh, Jean Koclas, Robert Roy
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3D Computer Visualization and Animation of CANDU Reactor Core

T. Qian, M. Echlin, P. Tonner, B. Sur
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Fusion Research's Demise in Canada--Another Avro-Arrow?

Richard Bolton
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Instrument Development for Safeguards Implementation on Spent CANDU Fuels in Korea

Young-Gil Lee, Hong-Ryul Cha, Won Woo Na, Wan Ki Yoon
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Waste Management Study for the Disposition of Spent Uranium-Metal Fuel from the Democratic People's Republic of Korea (DPRK)

Michael Attas, Y. Ates, P. Baumgartner, J. Garroni, L. Johnson, R. Lesco, J. Tait
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Quality Assurance Implementation and Effectiveness for CANDU 9 Program

J. Huterer
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Three Mile Island Litigation 20 Years Later: Any Lessons for Canadian Utilities?

Martin Reesink
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The Y2K Program for Scientific-Analysis Computer Programs at AECL

Jad Popovic, Cheryl Gaver, Dawn Chapman
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