ANS / Publications / Journals / Nuclear Technology

Interaction of Iodine with Preoxidized Stainless Steel

J. Abrefah, H. F. G. De Abreu, F. Tehranian, Y. S. Kim, D. R. Olander

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 137-144

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34918

Incipient Fault Detection and Identification in Process Systems Using Accelerated Neural Network Learning

Alexander G. Parlos, Jayakumar Muthusami, Amir F. Atiya

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 145-161

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34919

TRACG Transient Analysis Code—Three-Dimensional Kinetics Model Implementation and Applicability for Space-Dependent Analysis

Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu, Shigeo Ebata, James C. Shaug, Bharat S. Shiralkar

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 162-183

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34920

The Optimization of Squared-Off Cascades for Isotope Separation

Chuntong Ying, Edward Von Halle

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 184-189

Technical Paper / Enrichment and Reprocessing / dx.doi.org/10.13182/NT94-A34921

Scaling Laws and Design Aspects of a Natural-Circulation-Cooled Simulated Boiling Water Reactor Fuel Assembly

Rudi Van De Graaf, T. H. J. J. Van Der Hagen, Robert F. Mudde

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 190-200

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34922

Sandor Benedek

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 201-215

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34923

An Assessment of the Critical Heat Flux Approaches of Thermal-Hydraulic System Analysis Codes Using Bundle Data from the Heat Transfer Research Facility

Min Lee, Lih-Yih Liao

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 216-230

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34924

A Modeling Study of the PMK-NVH Integral Test Facility

Borut Mavko, Iztok Parzer, Stojan Petelin

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 231-252

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34925

On a Simplified Two-Phase Slug Flow Model

Yu-Wen Wang, Bau-Shei Pei, Wei-Keng Lin

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 253-260

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34926

The Effect of Dissolved Gas Bubble Nucleation on Natural Convection Heat Transfer in Narrow Channels

Wei-Wu Chao, Jay F. Kunze, Weimin Dai, Sudarshan K. Loyalka

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 261-270

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34927

Empirical Model Development and Validation with Dynamic Learning in the Recurrent Multilayer Perceptron

Alexander G. Parlos, Kil T. Chong, Amir F. Atiya

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 271-290

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34928

Evaluation of the Reactivity Expansion Defect for Small Solid-Core Reactors and Components

Salim Jahshan, Samim Anghaie

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 291-292

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT94-A34929

Thermal Performance Test of a Coaxial Double-Tube Hot-Gas Duct

Ikuo Ioka, Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Kunihiko Suzuki

Nuclear Technology / Volume 105 / Number 2 / February 1994 / Pages 293-299

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34930