Nuclear Technology -- ANS / Publications / Journals / Nuclear Technology

Jump to:

Number 1
Number 2

Number 3

Number 1

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT77-A35397

Number 2

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT97-A35388

Number 3

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 | 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 | 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 | 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 | 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 | 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
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 | 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 | doi.org/10.13182/NT97-A35406

Volume 119

Number 1

Number 2

Number 3