ANS / Publications / Journals / Nuclear Science and Engineering

Review of European Thermal-Hydraulic Calculational Methods for Thermal Reactors

M. A. Porracchia, M. M. Reocreux, M. C. Rousseau

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 375-379

Technical Paper / dx.doi.org/10.13182/NSE88-A23569

An Implicit Method to Speed Up WCOBRA/TRAC

K. Takeuchi, M. Y. Young

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 380-384

Technical Paper / dx.doi.org/10.13182/NSE88-A23570

The ARTEC Code: An Algorithm for Solving Thermal-Hydraulic Equations in Complex Geometries

R. D. Lonsdale

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 385-392

Technical Paper / dx.doi.org/10.13182/NSE88-A23571

A Chaotic Attractor in a Periodically Forced Two-Phase Flow System

Rizwan-uddin, J. J. Doming

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 393-404

Technical Paper / dx.doi.org/10.13182/NSE88-A23572

Parallel Algorithms for Fluid Dynamics Problems

J. S. B. Gajjar

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 405-413

Technical Paper / dx.doi.org/10.13182/NSE88-A23573

A Time-Dependent Nodal-Integral Method for the Investigation of Bifurcation and Nonlinear Phenomena in Fluid Flow and Natural Convection

G. L. Wilson, R. A. Rydin, Y. Y. Azmy

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 414-425

Technical Paper / dx.doi.org/10.13182/NSE88-A23574

Development of an Expert System for the Design Synthesis and Reliability Assessment

Bok Ki Min, Soon Heung Chang

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 426-434

Technical Paper / dx.doi.org/10.13182/NSE88-A23575

Expert Systems for the Analysis of Transients on Nuclear Reactors: SEXTANT, A General-Purpose Physical Analyzer

N. Barbet, M. Dumas, G. Mihelich, Y. Souchet, J. B. Thomas

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 435-439

Technical Paper / dx.doi.org/10.13182/NSE88-A23576

The Potential for Expert System Support in Solving the Pressurized Water Reactor Fuel Shuffling Problem

B. M. Rothleder, G. R. Poetschat, W. S. Faught, W. J. Eich

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 440-450

Technical Paper / dx.doi.org/10.13182/NSE88-A23577

Analysis of a Delayed Return to Full Power Using a Three-Dimensional Simulator

A. Charlier, M. Doucet, C. Vandenberg, W. de Roovere, J. Bens

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 451-457

Technical Paper / dx.doi.org/10.13182/NSE88-A23578

Multidimensional Effects in Optimal Control Analysis for Nuclear Reactors

Gregory D. Wyss, Roy A. Axford

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 458-466

Technical Paper / dx.doi.org/10.13182/NSE88-A23579

Neutron Spectral Analysis of the Caorso Boiling Water Reactor Cavity and Sacrificial Shield Penetrations and Comparison with the Irradiation Experiment Results

P. Barbucci, G. Mariotti, N. Cerullo, P. Riscossa⁺ A. Cesana, M. Terrani, G. Sandrelli

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 467-478

Technical Paper / dx.doi.org/10.13182/NSE88-A23580

Intercomparison of Reaction Rate and Gamma Scan Measurements and Calculation Analyses in a Pressurized Water Reactor

B. M. Rothleder

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 479-489

Technical Paper / dx.doi.org/10.13182/NSE88-A23581

The Superphénix-2 Project

J. P. Marcon, H. Sztark

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 490-495

Technical Paper / dx.doi.org/10.13182/NSE88-A23582

Experimental Study of the Large-Scale Axially Heterogeneous Liquid-Metal Fast Breeder Reactor at the Fast Critical Assembly —Power Distribution Measurements and Their Analyses

Susumu Iijima, Makoto Ōbu, Tamotsu Hayase, Akio Ohno, Tatsuo Nemoto, Shigeaki Okajima

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 496-506

Technical Paper / dx.doi.org/10.13182/NSE88-A23583

The Integral Fast Reactor Concept: Physics of Operation and Safety

D. C. Wade, Y. I. Chang

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 507-524

Technical Paper / dx.doi.org/10.13182/NSE88-2

Analyses of Reactor Physics Experiments in the Kyoto University Critical Assembly

Seiji Shiroya, Keiji Kanda, Keichiro Tsuchihashi

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 525-537

Technical Paper / dx.doi.org/10.13182/NSE88-7

Analysis of Large Liquid-Metal Fast Breeder Reactor Critical Experiments by Improved Methods

Toshikazu Takeda, Hironobu Unesaki, Tamotsu Sekiya, Keisho Shirakata

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 538-548

Technical Paper / dx.doi.org/10.13182/NSE88-A23586

Results and Implications of the Experimental Breeder Reactor II Inherent Safety Demonstration Tests

H. P. Planchon, G. H. Golden, J. I. Sackett, D. Mohr, L. K. Chang, E. E. Feldman, P. R. Betten

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 549-557

Technical Paper / dx.doi.org/10.13182/NSE100-549