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Home / Publications / Journals / Nuclear Technology / Volume 95 / Number 1

Volume 95

Number 1

A Rule-Based Expert System for Automatic Control Rod Pattern Generation for Boiling Water Reactors

Lian Shin Lin, Chaung Lin

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 1-8

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34563

In-Core Nuclear Fuel Management Optimization for Pressurized Water Reactors Utilizing Simulated Annealing

David J. Kropaczek, Paul J. Turinsky

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 9-32

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-1-9

Prediction of Mass Transfer and Heat Evolution of Purex Pulsed Columns by the DYNAC Computer Model

Masahiro Nabeshima

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 33-43

Technical Paper / Enrichment and Reprocessing / dx.doi.org/10.13182/NT91-A34565

Advanced Remote Decontamination Techniques Reduce Costs and Radiation Doses

Y. Bruce Katayama, Langdon K. Holton, Jr., Galen N. Buck, James F. Hutchens, Mark S. Culverhouse

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 44-53

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34566

Preliminary Assessments for Disposal of High-Level Waste Within Small Islets

Fu-Long Chen, Shih-Hai Li, Ge-Ping Yu

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 54-63

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34567

A DSNP Movable Boundary U-Tube Steam Generator Model

Doron Gal, David Saphier, Ezra Elias

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 64-76

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34568

Two-Phase Flow Interfacial Drag for Once-Through Steam Generators

Yassin A. Hassan, Omar Rais

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 77-86

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34569

Verification of Using a Single Void Fraction Sensor to Identify Two-Phase Flow Patterns

Y. W. Wang, B. S. Pei, W. K. Lin

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 87-94

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34570

Determining Wall Superheat Under Fully Developed Nucleate Boiling in Plate-Type Research Reactor Cores with Low-Velocity Upward Flows

Mohamed Belhadj, Tunc Aldemir, Richard N. Christensen

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 95-102

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34571

Application of Mixture Drift Flux Equations to Vertical Separating Flows

Kyungdoo Kim, J. Michael Doster

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 103-115

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34572

Designing a Knowledge-Based Operator Support System for Practical Applications

Yushi Fujita, Makoto Tohyama, Ichiro Yanagisawa, Toshio Ida, Hiroshi Arikawa

Nuclear Technology / Volume 95 / Number 1 / July 1991 / Pages 116-128

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT91-A34573

 

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