ANS / Publications / Journals / Nuclear Technology

Neural Network Model for Estimating Departure from Nucleate Boiling Performance of a Pressurized Water Reactor Core

Hyun-Koon Kim, Seung-Hyuk Lee, Soon-Heung Chang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 111-122

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34773

Radis—a Regional Nuclear Accident Consequence Analysis Model for Hong Kong

Mankit Ray Yeung, Eric M. K. Ching

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 123-139

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34774

A Comparative Study of Nuclear Accident Consequences for Hong Kong

Eric M. K. Ching, Mankit Ray Yeung

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 140-148

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34775

A Probabilistic Safety Criterion for Core Melt Frequency Based on the Distribution of the Public’s Safety Goals

Ki-Yong Ra, Byong-Whi Lee, Soon-Heung Chang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 149-158

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34776

Abnormal Event Identification in Nuclear Power Plants Using a Neural Network and Knowledge Processing

Yukiharu Ohga, Hiroshi Seki

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 159-167

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34777

The Use of Nonlinear Regression Analysis for Integrating Pollutant Concentration Measurements with Atmospheric Dispersion Modeling for Source Term Estimation

Leslie L. Edwards, Robert P. Freis, Linda G. Peters, Paul H. Gudiksen, Sergei E. Pitovranov

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 168-180

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34778

RELAP5 Modeling of the Westinghouse Model D4 Steam Generator

Borut Mavko, Stojan Petelin, Oton Gortnar

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 181-192

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34779

Some Aspects of Nuclear Power Plant Safety Under War Conditions

Andrej Stritar, Borut Mavko, Janez Sušnik, Božidar Šarler

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 193-201

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34780

A Power-Rate-Dependent Model for Pellet/Cladding Mechanical Interaction

Chlng-Kong Chao, Che-Chung Tseng

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 202-211

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34781

An Application of the Concept of Limit of Expenditures in Risk Reduction Measures to the Brazilian Case

L. F. Oliveira, J. E. Lima, P. F. Frutuoso E Melo

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 212-217

Technical Paper / Economic / dx.doi.org/10.13182/NT93-A34782

Fire Behavior and Filter Plugging During a Postulated Solvent Fire in the Extraction Process of a Nuclear Fuel Reprocessing Plant

Kazuichiro Hashimoto, Gunji Nishio, Kunihisa Soda

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 218-226

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34783

A Two-Fluid Two-Phase Model for Thermal-Hydraulic Analysis of a U-Tube Steam Generator

Huan-Jen Hung, Ching-Chang Chieng, Bau-Shei Pei, Song-Feng Wang

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 227-236

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34784

Transport Analysis of Several Cross-Section Libraries Used for Reactor Pressure Vessel Fluence Calculations

Alireza Haghighat, Ramana Veerasingam

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 237-243

Technical Note / Material / dx.doi.org/10.13182/NT93-A34785

RELAP5/MOD3 Simulation of the Water Cannon Phenomenon

W. S. Yeung, Jen Wu, R. T. Fernandez, R. K. Sundaram

Nuclear Technology / Volume 101 / Number 2 / February 1993 / Pages 244-251

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A34786