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No. 1 (1996): Fifth International Conference on Simulation Methods in Nuclear Engineering
Published:
1996-09-11
Articles
Dynamic Benchmarking of Simulation Codes
Robert E. Henry, Chan Y. Paik, George Hauser
PDF
Recent Rends in Methodlogies for CANDU Finite-Core Analysis at AECL
B. Rouben
PDF
Coupling Subroutine Version of ELOCA Code for High-Temperature Fuel Behaviour to CATHENA System Thermalhydraulics Code
L.N. Carlucci, J.R. Gauld, V.I. Arimescu, D.J. Richards
PDF
Overview of TUF Code for CANDU Reactors
W.S. Liu, R.K. Leung, J.C. Luxat
PDF
Modelling Inlet or Outlet Feeder Voiding and Fuel Simulator Cooling Under Natural Circulation Conditions in the RD-14M Loop
P. Gulshani, H.M. Huynh
PDF
Assessment of CATHEA for Simulating Two-Phase Water Hammer
T.G. Beuthe
PDF
Pre- and Post-Test CATHENA Simulations for RD-14M Critical Break Experiments
E.J.M. Yetman, T.V. Sanderson
PDF
A Numerical Sutdy of the Influence of the Void Drift Model on the Predictions of the ASSERT Subchannel Code
P. Tye, A. Teyssedou, N. Troche, J. Kitley
PDF
Effect of the Position of an Orifice with Respect to an Elbow on Counter-Current Flooding
S. Bedard, A. Teyssedou, P. Tye, W. Midvidy
PDF
An Investigation of the Local Non Uniformities in the Ignalina RBMK-1500 Reactor Core Characteristics
B.R. Sehgal, A. Balygin
PDF
Distributed Fuel-Management Computation using RFSP, WIMS-AECL and PRVM
P.J. Laughton, D.A. Jenkins
PDF
Investigation of Error Sources during Core Reactivity Measurements
Roger Blake
PDF
Parallel Accelration and Rebalancing Schemes for Solving Transport Problems Using PVM
A. Qaddouri, R. Roy, B. Goulard
PDF
Fuel Management Study of Refuelling of One-Quarter and One-Half of the Core at Point Lepreau
M.A. Shad, H.C. Chow, C.W. Newman, R.W. Sancton
PDF
Sedapsim Reactor Systems Analyzer for Design and Beyond Design Basis Accident Conditions
C.M. Allison, D.L. Hagrman
PDF
Probabilistic Analysis of Maximum Channel Power Error - a Parametric Study
A.P. Firla, P. Sermer
PDF
A Probabilistic Approach to Channel-Power-Limit and Bundle-Power-Limit Compliance Analysis
F.A.R. Laratta, H.C. Chow, E.G. Young, C.W. Newman, R.E. Stone
PDF
CANDU 9 Moderator Temperature Predcitions for Steady State and Accident Scenarios Using MODTURC-CLAS
W.M. Collins, B. Wu
PDF
Using Deterministic Methods for Research Reactor Studies
E. Varin, S. Noceir, R. Roy, D. Rozon, C. Guertin
PDF
Application of Uncertainty Analyses with the MAAP4 Code
K. Nagashima, M. Alammar, H.C. DaSilva, R.E. Henry, M. Kenton, D. Kuhntenia, M. Kwee, W. Ranval
PDF
Development of the CAT Code-YGN 5 and 6 CVCS Analysis Tool
S.W. Kim, S.H. Sohn, J.T. Seo, S.K. Lee
PDF
Simulation of Relief Valve Dynamic Behaviour
K.F. Hau, N.Y. Lee, A. Usmani
PDF
Validation of FORTRAN Emulators for the G2 Varian Control Programs
Guy Delorme
PDF
The Reactor Trainer: State-of-the-Art Classroom Learning
Robert G. Stater
PDF
Simulation-Based Reactor Control Design Methodology for CANDU 9
M.K. Kattan, M.J. MacBeth, W.F. Chan, K.Y. Lam
PDF
Simulation of Reactor Power Cutback System Tests for YGN 3 and 4
Jong-Tae Seo, Suk-Whun Sohn, Song-Keun Lee