ANS / Publications / Journals / Nuclear Technology

Impact of Wind Velocity on the Performance of the RVACS Decay Heat Removal System

Constantine P. Tzanos

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 1-10

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT77-A35390

Turbulence Prediction in Two-Dimensional Bundle Flows Using Large-Eddy Simulation

Yassin A. Hassan, Wael A. Ibrahim

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 11-28

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT77-A35391

Simulation of Loss of the Residual Heat Removal System of BETHSY Integral Test Facility Using CATHARE Thermal-Hydraulic Code

Yassin A. Hassan, Andrey A. Troshko

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 29-37

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT77-A35392

Modeling Gamma-Ray Dose Rate from a Spent Pressurized Water Reactor Fuel Assembly

Ahmet Bozkurt, Nicholas Tsoulfanidis

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 38-47

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT77-A35393

Hypermedia Integration of Information Resources for Nuclear Plant Operations

Lefteri H. Tsoukalas, Robert E. Uhrig

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 48-62

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT77-A35394

A Personal Computer-Based On-Line Signal Validation System for Nuclear Power Plants

Ali S. Erbay, Belle R. Upadhyaya

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 63-75

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT77-A35395

Survey of Artificial Intelligence Methods for Detection and Identification of Component Faults in Nuclear Power Plants

Jaques Reifman

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 76-97

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT77-A35396

Modification of Condensation Heat Transfer Model of RELAP5/MOD3.1 for the Simulation of Secondary Condensers

Hyoung Tae Kim, Hee Cheon No

Nuclear Technology / Volume 119 / Number 1 / July 1997 / Pages 98-104

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT77-A35397

Two-Group, Flux-Coupled Xenon Oscillation Model with an Equation System of Axial Difference Parameters

Jae Seung Song, Nam Zin Cho

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 105-111

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35379

Core Makeup Tank Behavior Observed During the Rosa-AP600 Experiments

Taisuke Yonomoto, Masaya Kondo, Yutaka Kukita, L. Scott Ghan,, Richard R. Schultz

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 112-122

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35380

Advanced Plutonium Fuel Assembly: An Advanced Concept for Using Plutonium in Pressurized Water Reactors

André Puill, Jean Bergeron

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 123-140

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35381

Some Specific Aspects of Homogeneous Americium-and Neptunium-Based Fuels Transmutation Through the Outcomes of the Superfact Experiment in Phénix Fast Reactor

Claude Prunier, François Boussard, Lothar Koch, Michel Coquerelle

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 141-148

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT97-A35382

Compatibility of the Ultraviolet Light-Ozone System for Laundry Waste Water Treatment in Nuclear Power Plants

Toshiaki Matsuo, Takashi Nishi, Masami Matsuda, Tatsuo Izumida

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 149-157

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35383

Corflow: A Code for the Numerical Simulation of Free-Surface Flow

Ralf Wittmaack

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 158-180

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35384

Signal Validation Using an Adaptive Neural Fuzzy Inference System

J. Wesley Hines, Darryl J. Wrest, Robert E. Uhrig

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 181-193

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT97-A35385

Melcor Self-Initialization Algorithm for Pressurized Water Reactors and Its Importance in Accident Analysis

Chun-Sheng Chien, Shih-Jen Wang, Te-Chuan Wang

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 194-200

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35386

Effect of Operating Cycle and Fuel Burnup on Isotopic Composition and Decay Characteristics of Irradiated Mtr-Type Low-Enriched Uranium Fuel

Liaquat Ali Khan, Nasir Ahmad

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 201-210

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35387

Maximum Heat Transfer to Metallic-Liquid Flows from a Cluster of Vertical, Parallel-Plate Channels Heated Symmetrically

Antonio Campo, Gong Li

Nuclear Technology / Volume 119 / Number 2 / August 1997 / Pages 211-216

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35388

Implications of the Rosa/AP600 High- and Intermediate-Pressure Test Results

Louis M. Shotkin, Yutaka Kukita

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 217-234

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35399

RELAP5 Analysis of Gravity-Driven Core-Cooling Experiments with Pactel

Reijo Munther, Juhani Vihavainen, Heikki Kalli, Jyrki Kouhia, Vesa Riikonen

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 235-243

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35400

Effect of RELAP5/MOD3.2 User Options on Calculated Results

John D. Burtt, Louis M. Shotkin, Joseph L. Staudenmeier

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 244-268

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35401

Feature Extraction for Artificial Neural Network Application to Fabricated Nuclear Fuel Pellet INSPECTION

Shahla Keyvan, Mark L. Kelly, Xiaolong Song

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 269-275

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35402

Parallel Adaptive Evolutionary Algorithms for Pressurized Water Reactor Reload Pattern Optimizations

Joachim K. Axmann

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 276-291

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35403

Introduction to Special Section on Nuclear Criticality Safety

Robert Busch

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Page 293

dx.doi.org/10.13182/NT97-A35404

Criticality Safety Evaluation of Shutdown Diffusion Cascade Coolers

Lane S. Paschal, C. L. Bentley,† Michael E. Dunn,‡ S. Goluoglu, R. E. Pevey, H. L. Dodds

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 295-305

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT97-A35405

Development of a Continuous Energy Version of Keno V.a

Michael E. Dunn, C. L. Bentley, † S. Goluoglu, Lane S. Paschal‡, L. M. Petrie, H. L. Dodds

Nuclear Technology / Volume 119 / Number 3 / September 1997 / Pages 306-313

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT97-A35406