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Volume 97

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Number 1

Development of an Expert System for Failure Diagnosis of Primary Side Systems

Se-Woo Cheon, Han-Gon Kim, Wan-Joo Kim, Bok-Ki Min, Soon-Heung Chang, Hak-Yeong Chung

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 1-15

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34621

A Technique for the Selection of the Fuel Pin Diameter for a Uranium/Zirconium Alloy—Fueled Pressurized Water Reactor

Dale B. Lancaster, Robert L. Marsh, Daniel B. Bullen, Holger Pfeifer, C. Steve Erwin, Alan E. Levin+

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 16-26

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34622

A Two-Step Method for Developing a Control Rod Program for Boiling Water Reactors

Mehmet S. Taner, Samuel H. Levine, Ming-Yuan Hsiao

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 27-38

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34623

Framework for Computer-Aided Systems Design

Walter H. Esselman

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 39-51

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34624

On-Line Test of Signal Validation Software on the LOBI-MOD2 Facility in Ispra, Italy

Johannes Prock, Eggert Ohlmer, Michael Labeit

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 52-62

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34625

On-Line Radioiodine Measurement Using Hot Cell Effluent Gases of a Radiopharmaceutical Production Facility

Byung S. Lee, William A. Jester, Joseph M. Olynyk

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 63-70

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34626

Chemical Behavior of Radioiodine in Boiling Water Reactor Systems II: Effects of Hydrogen Water Chemistry

Chien C. Lin

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 71-78

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34627

Nonlinear Identification of Process Dynamics Using Neural Networks

Alexander G. Parlos, Amir F. Atiya, Kil T. Chong, Wei K. Tsai

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 79-96

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34628

Hydrogen Generation Behavior in the LOFT FP-2 and Other Experiments: Comparative Assessment for Mitigated Severe Accident Conditions

August W. Cronenberg

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 97-112

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT92-A34629

Analysis of Counterpart Tests Performed in Boiling Water Reactor Experimental Simulators

Roberto Bovalini, Francesco D’Auria, Antonio De Varti, Piero Maugeri, Marino Mazzini

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 113-130

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34630

Active Neutron Multiplication Method for Fuel Lattices in Water

Makoto Ueda, Shigeto Kikuchi, Hironori Kumanomido, Takeshi Seino

Nuclear Technology / Volume 97 / Number 1 / January 1992 / Pages 131-141

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT92-A34631

Number 2

Safety Design Study of Fast Breeder Reactors in Japan

Masanori Miura, Tatsutoshi Inagaki

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 145-152

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34611

Development of Design Guidelines for Seismically Isolated Nuclear Reactors and Research and Development Work Performed by ENEA

Alessandro Martelli, Massimo Forni, Maurizio Indirli, Paolo Masoni, Bruno Spadoni, Giuseppe Bonacina, Giacomo di Pasquale, Tito Sanò, Emil L. Gluekler

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 153-169

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34612

Application of Neural Networks for Sensor Validation and Plant Monitoring

Belle R. Upadhyaya, Evren Eryurek

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 170-176

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34613

Equilibrium and Nonequilibrium Partition Coefficients of Volatile Fission Products Between Liquid Sodium and the Gas Phase

Kazuo Haga, Yukinori Nishizawa, Toshio Watanabe, Shinya Miyahara, Yoshiaki Himeno

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 177-185

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34614

In-Vessel Thermohydraulics Evaluation of an Unprotected Transient Overpower Accident and Delayed Neutron Precursor Concentration Transport Analysis Using a Multidimensional Code

Toshiharu Muramatsu, Hisashi Ninokata

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 186-197

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34615

Performance of Metal and Oxide Fuel Cores During Accidents in Large Liquid-Metal-Cooled Reactors

Peter H. Royl, James E. Cahalan, Günter Friedel, Günter Kussmaul, Jean Moreau, Maurice Perks, Roald A. Wigeland

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 198-211

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34616

Sodium Aerosol Release Rate and Nonvolatile Fission Product Retention Factor During a Sodium-Concrete Reaction

Shinya Miyahara, Kazuo Haga, Yoshiaki Himeno

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 212-226

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34617

Behavior of Breached Mixed-Oxide Fuel Pins During Off-Normal High-Temperature Irradiation

Robert V. Strain, Kenny C. Gross, John D. B. Lambert, Richard P. Colburn, Toshihiro Odo

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 227-240

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34618

A Cost/Risk Framework for Evaluation of Nuclear Waste Management Strategies

William E. Kastenberg, Clyde D. Newman

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 241-251

Technical Paper / Economic / dx.doi.org/10.13182/NT92-A34619

Number 3

Generation of a Library for Reactor Calculations and Some Applications in Core and Safety Parameter Studies of the 3-MW Triga Mark-II Research Reactor

S. I. Bhuiyan, Anisur Rashid Khan, M. M. Sarker, M. Rahman, Z. Gulshan Ara, M. Musa, M. A. Mannan, I. Mele

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 253-263

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34633

An Axially Multilayered Low Void Worth Liquid-Metal Fast Breeder Reactor Core Concept

Takanobu Kamei, Mitsuaki Yamaoka

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 264-271

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34634

Nuclear Power Plant Status Diagnostics Using an Artificial Neural Network

Eric B. Bartlett, Robert E. Uhrig

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 272-281

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34635

Thermal-Hydraulic Analysis of a Hypothetical Complete Failure of One Shroud Access Hole in a Boiling Water Reactor

Lih-Yih Liao

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 282-293

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34636

Depressurization Accidents in a Medium-Sized High-Temperature Gas Reactor: Break Size Parametric Study

Shlomo Ron, Judah Tzoref, Doron Gal

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 294-302

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34637

Chemotoxicity of Nuclear Waste Repositories

Bernd Buchheim, Lars Persson

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 303-315

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34638

Zircaloy Cladding Rupture During Repository Storage

Lakshman Santanam, Suresh Raghavan, Bryan A. Chin

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 316-322

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34639

Modeling for Migration of a Redox-Sensitive Radionuclide in Engineered Barriers

Joonhong Ahn, Shinichi Nakayama

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 323-335

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34640

Dynamic Strain-Aging Effect on Fracture Toughness of Vessel Steels

Sung Sik Kang, In Sup Kim

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 336-343

Technical Paper / Material / dx.doi.org/10.13182/NT92-A34641

Three-Dimensional Thermal Aspects of Aluminum Fuel Elements

Robert P. Wadkins, Richard G. Ambrosek

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 344-351

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34642

Development of an Efficient Three-Dimensional Reactor Core Model for Simulator Applications

Mankit Ray Yeung, Guo Bing Jiang

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 352-361

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34643

Life Testing of a Low-Voltage Air Circuit Breaker to Assess Age-Related Degradation

Mano Subudhi

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 362-370

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34644