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Volume 111

Number 1

Table of Contents

A Parametric Study of the Steady-State Operational Characteristics of the Ohio State University Natural Circulation, Indirect-Cycle, Inherently Safe Boiling Water Reactor

Hikmet S. Aybar, Tunc Aldemir, Richard N. Christensen

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 1-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35140

An Estimation of Core Damage Frequency of a Pressurized Water Reactor During Midloop Operation Due to Loss of Residual Heat Removal

Chun-Chang Chao, Chi Ta Chen, Min Lee

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 23-33

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35141

A Comparison of the RELAP5/MOD3 Code with the IIST Natural Circulation Experiments

Yuh-Ming Ferng, Chien-Hsiung Lee

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 34-45

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35142

Predicting the Severity of Nuclear Power Plant Transients Using Nearest Neighbors Modeling Optimized by Genetic Algorithms on a Parallel Computer

Jie Lin, Yair Bartal, Robert E. Uhrig

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 46-62

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35143

Effects of Different Parameters on the Densities of Uranium Dioxide and Uranium Dioxide-Gadolinium Oxide Fuels Produced by the Sol-Gel Technique

G. Gündüz, İ. Uslu, I. Önal, H. H. Durmazuçar, T. Öztürk, A. A. Akşit, B. Kopuz, F. Can, Ş. Can, R. Uzmen

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 63-69

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35144

Measured Insensitivity of Memory Devices to Various Nuclear Radiations

Alireza Behbahani, James N. Anno

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 70-79

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35145

Evaporation Reduction from Tritiated Water Pools

M. T. Pauken, M. F. Dowling, B. K. Kamboj, S. M. Jeter, S. I. Abdel-Khalik

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 80-91

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35146

Application of Detonation Wave Theory to Subcritical Vapor Explosions

Luder Tibkin, Mahmoud El-Beshbeeshy, Riccardo Bonazza, Michael L. Corradini

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 92-104

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35147

Failed Fuel Detection in Reactor Coolant Using Radioiodine Measurement

R. K. Gopalakrishnan, P. M. Ravi, S. K. Prasad, M. R. Iyer

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 105-108

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35148

Nuclear Fuel Management Optimization Using Genetic Algorithms

Michael D. DeChaine, Madeline Anne Feltus

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 109-114

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35149

Application of Reliability-Centered Maintenance to Boiling Water Reactor Emergency Core Cooling Systems Fault-Tree Analysis

Young A. Choi, Madeline Anne Feltus

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 115-121

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT95-A35150

Neutronics and Engineering Design of the Aqueous-Slurry Accelerator Transmutation of Waste Blanket

Carl A. Beard, John J. Buksa, Michael W. Cappiello, J. Wiley Davidson, Jay S. Elson, John R. Ireland, Robert A. Krakowski, Burt J. Krohn, William C. Sailor, Joseph L. Sapir

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 122-132

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35151

Long-Lived Waste Transmutation in Reactors

Jean Tommasi, Marc Delpech, Jean-Paul Grouiller, Alain Zaetta

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 133-148

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT111-133

Transmutation of High-Level Radioactive Waste by a Charged-Particle Accelerator

Hiroshi Takahashi

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 149-162

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35153

Vitrification of Fission Product Solutions: Investigation of the Effects of Noble Metals on the Fabrication and Properties of R7T7 Glass

M. Puyou, N. Jacquet-Francillon, J. P. Moncouyoux, C. Sombret, F. Teulon

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 163-168

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35154

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