Published: 1988-04-26

Articles

Transdec: A Program to Calculate the Extra Decay Energy Generated in a Power Transient

C.R. Calabrese, C.R. Boss, B. Rouben

1.1

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A Universal Driver for Collision Probability and Response Matrix Transport Codes

Guy Marleau, Alain Hebert

1.2

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From Platinum to Mercury: The Alchemist's Nightmare

K.J. Serdula, G. Parent

1.3

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Calculating Three-Dimensional Neutronic Transients on Microcomputers

B. Rouben, C.R. Calabrese

1.4

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A Method for Simulating Grey Slabs in CANDU Reactors

D.B. Buss, A.R. Dastur

1.5

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DERREP: A Computer Code for the Calculation of Decay Heat in CANDU Reactor Nuclear Fuel

R.P. Steadman, J.V. Marczak, M.K. O'Neill

1.6

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Simple Functions for the Fast Approximation of Light Water Thermodynamic Properties

W.J. Garland, B.J. Hand

2.1

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Piecewise Polynomial Approximation of Thermodynamic Properties of Heavy Water

Y. Liner, B.N. Hanna, D.J. Richards

2.2

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Modelling of Nonhomogeneous Nonequilibrium Critical Two-Phase Flow

S.M. Sami

2.3

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Numerical Predictions of Two-Phase Flow Parameters in Inverted U-tubes under Reflux Condensation

R. Girard, J.S. Chang

2.4

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Investigation of CCFL in Pipe Elbows

L. Thomson, V.S. Krishnan, M. Kawaji

2.5

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Prediction of Pressurizer Transient by the IDRIFF Two-phase Simulation Code

R. Sollychin, J.S. Chang, W.J. Garland

3.1

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The Dynamic Simulation of a Two-Node Non-Equilibrium 600MW CANDU Pressurizer System

Haldun O. Tezel, Daniel A. Menely

3.2

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MISSFINCH: Models for Steady Stratified Flow in CANDU Headers

P. Gulshani

3.3

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Steady-State Two-Phase Header Flow Mndcl

H.G.O. DeMan, Y. Feyginberg, W.I. Midvidy

3.4

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GENHTP - A New Heat Transfer Package for CATHENA

J.P. Mallory, P. Yuen, C.B. So

3.5

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Reactor Operator Companion for CANDU Heat Transport Systems

W.J. Garland, J.W.D. Anderson, J.D. Hoskins

4.1

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CATHENA Study of Large LOCA Channel Behaviour

S.D. Grant, R.L. DaSilva

4.2

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The Effect of Fuel Heat Transfer on Early Void Production Following a Large Pipe Break in CANDU Reactors

S.D. Grant, J.M. Hopwood

4.3

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Large Outlet Header Break Experiments in a CANDU-Type Heat Transport Loop

P.J. Ingham

4.4

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Implementation of a Post-Dryout Model in the ASSERT Subchannel Code

A. Tahir, S. Robinovitch, P.R. Thibeault

4.5

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Thermalhydraulic Plant Modelling of a CANDU Reactor Including Plant Control Systems using CATHENA

F.W. Barclay, D.J. Richards

4.6

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Safety Aspects of Nuclear Battery Reactor Design

James V. Donnelly

5.1

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Some Aspects of Modelling MAPLE-10 Fuel

S. Girgis, I.E. Oldaker, G.E. Gillespie

5.2

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Recent Developments in Static Reactor Physics Modeling Techniques used for the Maple Research Reactor Program

P.A. Carlson, H.J. Smith, R.J. Ellis, A.G. Lee

5.3

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Comparisons of the Steady-State and Transient Thermal Behaviours of UO,, U-A1 and U3Si-A1 MAPLE Research Reactor Fuels

R.J. Ellis, P.A. Carlson, H.J. Smith

5.4

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The Sensitivity of MAPLE-XI0 Core Reactivity to Variations in the Three-Dimensional Coolant Void Distribution

H.J. Smith

5.5

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Upper Bound Calculations of Aerosol Vapour Mass Concentrations in a CANDU Fuel Channel during Severe Fuel Damage Accidents

S.R. Mulpuru

6.1

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Pressure Challenges to CANDU Containment due to Hydrogen Combustion during Accidents

P. Klazek

6.2

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A Solution Scheme for Aerosol Transport Models

S.R. Vatsya, M. Razzaghi

6.3

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Integrated Aerosol and Thermalhydraulic Modelling

B.H. McDonald

6.4

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Effects of Antivibration Bars on the U-Bend Flow Distribution in Recirculating Steam Generators

L.N. Carlucci, J.M. Pietralik

7.1

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Techniques for the Estimation of Pressure Loss Coefficients of Bundle Junctions, Grid Spacers and Bearing Pads

S.C. Sutradhar, A. Tahir

7.2

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Simulation of the SPEL Small Scale Moderator Experiments Using the General Purpose Fluid-Flow Heat Transfer Code Phoenics

W.M. Collins

7.3

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Thermalhydraulic Simulations for Plate-Type Nuclear Fuel Elements

Helena E.C. Rummens, Jen-Shih Chang, Peter Ernst

7.4

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