Published: 1995-10-17

Articles

Comparison of Power Pulses from Homogeneous and Time-Average-Equivalent Models

T.K. De, B. Rouben
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Application of the Feedback Model for the History Base Using DRAGON

T. Sissaoui, Guy Marleau
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Analysis of the Fast-Neutron Spectrum Inside the Experimental Cavity of the NRU Mk4 FN Rod

Timothy C. Leung
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Validation of Physics Model of FARE Tool by Comparison of RFSP Flux Simulations with Measurements at Discrete Rebelling Steps

M.A. Shad
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Change in CANDU-6 Reactivity Following a Power Reduction at Low PHT Purity

J.J. Whitlock, M.R. Soulard, A. Baudouin
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REFUEL: Automated Refhel-ling Program for CANDU Reactors

Alan Gray
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The Reactor Physics Computer Programs in PC's Era

O. Nainer, D. Serghiuta
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The Burnable Poisons Utilization for Fissile Enriched CANDU Fuel Bundle

D. Serghiuta, O. Nainer
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The Application of the Goal Programming to CANDU Fuel Management Optimization

D. Serghiuta, O. Nainer
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Sensitivity of 238U Resonance Absorption to Library Multigroup Structure as Calculated by WIMS-AECL

P.J. Laughton, James V. Donnelly
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Application of the DONJON Reactor Code for Regulating System Simulations

E. Varin, Jean Koclas, R. Roy
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Hydrogen Distribution Studies Relevant to CANDU Containments

M. Krause, D.R. Whitehouse, C.K. Chan, S.C.A. Jones
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Modelling of Hydrogen Deflagration in a Vented Vessel

L. Wang, R.C. Wong
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Cell Size Spatial Convergence Analysis on GOTHIC Distributed Parameter Models for Studying Hydrogen Mixing Behaviour in CANDU Containments

K. Yim, R.C. Wong
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Hydrogen Distribution Analysis for CANDU 6 Containment Using the GOTHIC Containment Analysis Code

T.H. Nguyen, W.M. Collins
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An Improved Methodology for Addressing Coolant Inlet Temperature Variations When Calculating NOP Trip Set-Points

David Buchan
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Gas Resolution and Released Models in Reactor Thermal-Hydraulics

E. Zaltsgendler, W.S. Liu, R.K. Leung
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Experimental and Numerical Study of Single-Phase Heat Transfer Enhancement in a Tube

S. Doerffer, A.O. Banas, C.H. Wang
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ASSERT Software Quality Assurance, Benchmark Testing and Parametric Studies

J.C. Kiteley, M.B. Carver, G.M. Waddington, S.V. Junop
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ASSERT Validation Against the Stern Laboratory Pressure Drop Tests

G.M. Waddington, J.C. Kiteley, M.B. Carver
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Prediction Methods to Account For The Effect of Pressure-Tube Diametral Creep On Critical Heat Flux and Pressure Drop For A 37-Element Bundle String

L.H.K. Leung, D.C. Groeneveld, G. Hotte
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Detection of Damped Flow Oscillations in a CANDU 6 SOPHT Simulation using Noise Perturbations

Y. Gao, H.W. Hinds, P. Tonner, P. Kumli
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Some Aspects of Modelling CWIT Refill Test 1465 Using CATHENA

P. Han, W. Thompson, A. Galia
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CANDU-9 Nuclear Power Plant Simulator

Mahmoud Kattan, Mike MacBeth, Kwok Lam
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MAAP-CANDU Simulation of Severe Accidents in Darlington NGS

M.H. Choi, M.T. Kwee, R.K. Leung, S.G. Lie
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Fault Detection and Diagnosis Using Statistical Control Charts and Artificial Neural Networks

R. Leger, W.J. Garland, W.F.S. Poehlman
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Rapid Assessment of Atmospheric Releases for Nuclear Emergency Response Planning

R. DeWit, D. Spagnolo, S. Kupca
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Determination of Critical Break for Large Break Loss-of-Coolant Accident Analysis

J.D. Hoskins, W. Chan
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Large Break Loss-of-Coolant Accident Coincident with Loss of Class IV Power Analysis

P. Ta, W. Chan
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Darlington NGS Reactor Operation with Flux Tilt Impact on Neutron Overpower Protection

A.H. Oslinger, E.A. Attia
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In Core LOCA-s: Analytical Solution for the Delayed Mixing Model for Moderator Poison Concentration

A.P. Firla
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