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Volume 83

Number 1

Criticality Safety Evaluation for High-Density Spent-Fuel Storage Racks

Tien-Ko Wang, Szu-Li Chang, Shi-Ping Teng

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 5-15

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT88-A34170

The Growth of Hygroscopic Particles During Severe Core Melt Accidents

Jorma Jokiniemi

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 16-23

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT88-A34171

The Composition of NOx Generated in the Dissolution of Uranium Dioxide

Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 24-30

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT88-A34172

Out-of-Core Fuel Cycle Optimization for Nonequilibrium Cycles

Scott A. Comes, Paul J. Turinsky

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 31-48

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT88-A34173

Development and Active Demonstration of Acid Digestion of Plutonium- Bearing Waste

Herbert Wieczorek, Bernhard Oser

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 49-55

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT88-A34174

Identification of Two-Phase Flow Patterns by a Single Void Fraction Sensor

Y. W. Wang, C. H. King, B. S. Pei

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 56-64

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34175

IVA2 Verification: High-Pressure Gas Injection in a Liquid Pool

Nikolay Ivanov Kolev

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 65-80

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34176

Development of Computer Program DYNAM/US for Predicting Thermally Induced Flow Oscillations in Two-Phase Flow Systems

S. M. Sami, M. Kraitem

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 81-92

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34177

Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Bundles Under Loss-of-Coolant-Accident Conditions

Nicholas T. Saltos,* Richard N. Christensen, Tunc Aldemir

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 93-109

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34178