Published: 2002-11-04

Articles

Looking Through the Glass Clearly: Reviewing 30 years of Reactor Physics at Pickering

M.K. Oneill
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Nuclear Reactor Conceptual Design: Methodology For Cost-Effective Internalisation of Nuclear Safety

M. Gimenez, P. Grinblat, M. Schlamp
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Coolant Void Reactivity in a CANDU: A 2-D Transport/Diffusion Comparison

Guy Marleau, Elisabeth Varin
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HELIOS/DRAGON/NESTLE Codes' Simulation of Void Reactivity in a CANDU Core

Hisham N. Sarsour, Farzad Rahnema, Scott Mosher, Paul J. Turinsky, Dumitru Serghiuta, Guy Marleau, Tanguy Courau
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Best Estimate HELIOS/DRAGON/NESTLE Codes' Simulation of a LOCA Power Pulse for a Simplified CANDU-6 Core

Hisham N. Sarsour, Farzad Rahnema, Scott Mosher, Paul J. Turinsky, Dumitru Serghiuta, Guy Marleau, Tanguy Courau
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A Monte-Carlo Estimate of the Diffusion Coefficient for a CANDU Cell

Germina Ilas, Farzad Rahnema, Scott Mosher, Rudi Stamm'ler
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3D Heterogeneous Transport Calculations of CANDU Fuel with EVENT/HELIOS

Farzad Rahnema, Scott Mosher, Dan Ilas, Cassiano de Oliveira, Matthew Eaton, Rudi Stamm'ler
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Benchmark of WIMS-IST Against MCNP for CANDU Pressure Tube Fast Fluxes

R.E. Donders, S.R. Douglas
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HELIOS/DRAGON/NESTLE Codes’ Simulation of the Gentilly-2 Loss of Class 4 Power Event

Hisham N. Sarsour, Farzad Rahnema, Scott Mosher, Paul J. Turinsky, Dumitru Serghiuta, Guy Marleau, Tanguy Courau
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Bruce A Restart Initial Core Loading

Cuong Ngo-Trong, R.E. Sunderland
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SIMBRASS and Neutron Overpower Analysis

Michael Levine, Larry Blake, El-Tantaway Attia
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LOCA Analysis for the Basic Design of HANARO Fuel Test Loop

Dae-Young Chi, Chung-Young Lee, Bong-Shick Sim, Jun-Yun Kim, Kook-Nam Park, Cheol Park
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SDS-2 Modelling with DRAG_SHELL

M. Boubcher
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Porting RFSP-IST From HP-UX Platform to PC Platform

I. Dumitrache, W. Jenkins
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Least-Squares Fitting Method for On-Line Flux mapping of CANDU-PHWR

In Seob Hong, Chang Hyo Kim, Ho Chun Suk
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A Feasibility Study on CANFLEX-RU 4-BUNDLE Shift Scheme in CANDU-6 Reactor

Ho Chun Suk, Soon Young Kim, Chang Keun Jo
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Assesment of Selected Film-Boiling Prediction Methods

Y. Guo, D.C. Groeneveld, A. Vasic, L.K.H. Leung, S.C. Cheng
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A Methodology to Assess Transient Contact Heat Transfer Coefficient using Contact Boiling Test Data

H.Z. Fan, M. Shams, D.B. Sanderson
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A Study on CANDU Model Assessment of RELAP5/CANDU using RD-14M B9401 Multi-channel RIH Break Experiment

Yong Jin Cho, In-Goo Kim, Sukho Lee, Hho Jung Kim, Gyoo Dong Jeun
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The Film Boiling Look-Up Table: An Improvement in Predicting Post-CHF Temperatures

D.C. Groeneveld, L.K.H. Leung, A.Z. Vasic, Y.J. Guo, M. Cheng
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A Prediction Method For The Effect of Radial Heat-Flux Distribution on Critical Heat Flux in CANFLEX Bundles

L.K.H. Leung
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Development of MARS-h for the HANARO Safety Analysis

Cheol Park, Heon-il Kim, Gee-Yang Han, Won Jae Lee, Gwi-Seok Ha
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Effect Of Radial Heat Flux Distribution On Pressure Drops

M.K.Y. Ip, U.P.M. Senaratne, L.K.H. Leung
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Impact Strength Analysis of CANFLEX Fuel During CANDU-6 Normal Refueling

Moon-Sung Suk, Ho Chun Suk
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A New Human Reliability Analysis Method Using Dynamics Concept

Moosung Jae
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The Nature and Role of True Value in Monte Carlo Uncertainty Analyses with Application to BEAU Methodology

Paul Serner, Keith Weaver
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Effectiveness of Setback in Liquid Zone Control Pump Failure

Peter Schwanke
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Three-Dimensional Analyses of Fluid Flow and Heat Transfer for Moderator Integrity Assessment in PHWR

Seon Oh Yu, Manwoong Kim, Hho-Jung Kim
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Development and Validation of a Model for High Pressure Liquid Poison Injection for CANDU-6 Shutdown System No.2

Bo-Wook Rhee, Chang Joon Jeong, Jae Ho Choi, Seong-Yeon Yoo
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Steady State 3-D Simulation of CANDU6 Moderator Circulation Under the Normal Operating Condition

Churl Yoon, Bo Wook Rhee, Byung-Joo Min
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