ANS / Publications / Journals / Nuclear Technology

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

Sensitivity and Uncertainty Analysis of Integral Physics Parameters in High-Conversion Reactor Systems

John R. White, Thomas F. DeLorey

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 129-147

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34551

Corrosion Product Radionuclide Buildup in Fast Flux Test Facility Heat Transport System Cells

William F. Brehm, Robert L. Simons

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 148-155

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34552

Xenon Dynamics and Related Parameters in the Taiwan Research Reactor

Shih-Jen Wang, Ming-Song Lin

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 156-161

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34553

Effect of Flushing Boron During a Boiling Water Reactor Anticipated Transient Without Scram

Dragan Mirkovic, David J. Diamond

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 162-174

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34554

Theory and Verification of a Fuel Rod Mechanics Model Based on a Two-Dimensional Finite Element Method with Consideration of Fuel/Cladding Contact and Friction

Klaus L. Nissen

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 175-192

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34555

A Simple Nondestructive Measurement System for Spent-Fuel Management

Hermann Würz

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 193-206

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34556

Analysis of Cylindrical and Annular Pulsed Columns with Different Internal Plates in the Purex Process

Masahiro Nabeshima

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 207-218

Technical Paper / Environment and Reprocessing System / dx.doi.org/10.13182/NT91-A34557

Elaborated Constitutive Equations for Structural Analysis for Creep, Swelling, and Damage Under Irradiation

S. Murakami, M. Mizuno

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 219-227

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34558

Thermal-Hydraulic Systems Safety Analysis to Support the Design Process for the Advanced Neutron Source Reactor

C. D. Fletcher, L. S. Ghan

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 228-246

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34559

The Probability Density Function of the Total Departure from Nucleate Boiling Ratio

Ross C. Anderson

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 247-250

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34560

Analysis of DRACS and DRACS-RVACS Decay Heat Removal Experiments

Constantine P. Tzanos, Dean R. Pedersen

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 253-265

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34575

An Alarm Processing System for a Nuclear Power Plant Using Artificial Intelligence Techniques

Joon On Yang, Soon Heung Chang

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 266-271

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34576

Monte Carlo Methods, Models, and Applications to the Advanced Neutron Source

Everett L. Redmond II, John M. Ryskamp

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 272-286

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34577

Review of Experimental Results on Light Water Reactor Core Melt Progression

Richard R. Hobbins, David A. Petti, Daniel J. Osetek, Donald L. Hagrman

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 287-307

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34578

Probabilistic Safety Assessment of Support Systems for CANDU Stations

Hymie S. Shapiro

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 308-313

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34579

A Comprehensive Fission Gas Release Model Considering Multiple Bubble Sizes on the Grain Boundary Under Steady-State Conditions

Woan Hwang, Ho Chun Suk, Won Mok Jae

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 314-324

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34580

Safety Demonstration Tests of Hypothetical Explosive Burning in the Cell and Air Ventilation System in a Nuclear Fuel Reprocessing Plant

Gunji Nisio, Motoe Suzuki, Shigeo Mukaide, Junichi Takada, Michio Tsukamoto, Tadao Koike

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 325-336

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A34581

Design of a Neutron Gauge for the Detection and Measurement of Water Ingression in Flat Roofs

Hugues W. Bonin, Christopher J. Thorp

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 337-348

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT91-A34582

Development of a Parallelism Analysis Integrated System for a Fast-Running Pressurized Water Reactor Plant Predictive Simulator

Kazunori Sasaki, Hiroo Kanamaru, Mitsuo Tanaka

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 349-365

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT91-A34583

The Buildup of Confined Pressure at Salts in Decaying Radioactive Waste

K. H. G. Ashbee

Nuclear Technology / Volume 95 / Number 3 / September 1991 / Pages 366-371

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34584