Published: 1989-05-02

Articles

A Fully Implicit, Back-Substituted Algorithm for Thermalhydraulic Networks

R.J. Wilson, W.J. Garland
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Real-Time Simulation of CANDO Heat-Transport System

J.D. Hoskins, W.J. Garland
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An Iterative Method to Solve Large Sparse Linear Systems

S.R. Vatsya
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Parity Simulation Applied to Reactor Physics Nodal Theory Transient Analysis

P.J. Laughton
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Calculating Array Criticality Using Thomas's Limiting Surface Density Model

J.W. Thompson
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An Analytical Solution to the Equations for LongTerm Transport and Release of Fission Products

K.R. Weaver
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Recent Simulations of the Distribution of Flow and Temperature in Horizontal Bundles Using ASSERT-4

M.B. Carver, J.C. Kiteley, R.J. Morris
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CATHENA Prediction of MAPLE-X10 Performance During a Complete Pipe Severance

T.E. MacDonald, S.Y. Shim
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Investigation of Refilling Behaviour of a Simulated CANDO Feeder Pipe

R. Thuraisingham, M. Kawaji, J.C. Luxat
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MAPL3D Predictions of Three-Dimensional Flow Fields in a One-Flfth Scale Hydraulic Test Facility

D.K. Baxter, S.Y. Shim
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A Model for Two-Phase Redistribution in Dividing Two-Phase Flow

J.D. Ballyk, M. Shoukri
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Power Transient Following a Loss of Low Pressure Service Water Open System in Darlington NGS A

N. Roy, M.B. Gold, K.K. Fung
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The Effect of Loss of Regulation on the Severity of the Loss-of-Coolant Accident in the CANDO 6

M.H. Younis, S. Prawirosoehardjo, R. Calabrese, A.R. Dastur
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RFSP Simulation of a Reactor-History Slice Featuring Saturated Zone-Control Compartments

M.A. Dencer, B. Rouben, E. Young
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CANDU 600 Reactor Response to Localized Perturbations Such as Channel Fuelling

E. Young, R. Sancton, M. El-Hawary, R. Robinson
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Reactor Physics Simulation of Fast Reactivity Transients in the Nuclear Battery

James V. Donnelly
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SIMEX-77: A FORTRAN-77 Fuel Burnup History and Refuelling Simulation Program for Core Fuel Management at the Gentilly-2Nuclear Generating Station

Guy Hotte, Michel Beaudet, Jean Koclas, Gaston Pepin
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Application of a Monte-Carlo Simulation Code for the Research and Development of Self-.Powered Flux Detectors

T.C. Leung, R.J. Morris, S.J. Han
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PRESCON2 Simulation of the OECD/CSNI Containment International Standard Problem #23

W.M. Collins, R.A. Gibb
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Assessment of FFTF/MOTA and Thermal Reactor Irradiation Facilities for Advanced TritiumBreeder-Material Tests

R.E. Donders
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An Overview of Ontario Hydro's Nuclear Risk Assessment Program

V.M. Raina
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Real-Time Simulation of Electrical Distribution Systems

A. Abramovitch, N. Kratsios
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CIRENE Fuel Bundle Integrity Following a Feeder Break

P.N. Singh, R. Sejnoha, M. Tayal, G. Valli
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Transient Thermal Analysis of an Idealized Fuel Element

G.R. McGee, J.W. DeVaal
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An Improved Model for the Release of Fission Gas in CANDU Fuel

M. Tayal, A. Ranger
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Influence of Pellet Shapes on Sheath Strains: ELESTRES Predictions vs Irradiation Measurements

N.C. Singhal, M. Tayal, T.J. Carter
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Heat Flux Distribution on a Finned Fuel Pin

J.E. Kowalski, I.C. Lim, S.Y. Shim, P.J. Mills
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Simulation of a Closed Two-Phase Thermosiphon with the CATHENA Code

B.N. Hanna, B.G. Taylor
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A Method of Predicting CHF in Interconnected Subchannels

C.W. Snoek
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Two-Phase Pressure Drop Across Flow Obstructions

S.C. Sutradhar
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