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Home / Publications / Journals / Nuclear Technology / Volume 119 / Number 2

Volume 119

Number 2

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

 

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