ANS / Publications / Journals / Nuclear Technology

Reaction Kinetics of a Fission-Product Mixture in a Steam-Hydrogen Carrier Gas in the Phebus Primary Circuit

Laurent Cantrel, Elisabeth Krausmann

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 1-15

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-A3425

Transient Analysis and Dosimetry of the Tokaimura Criticality Incident

Christopher C. Pain, Cassiano R. E. de Oliveira, Antony J. H. Goddard, Matthew D. Eaton, Sarah Gundry, Adrian P. Umpleby

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 16-33

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-A3426

A MELCOR Application to Two Light Water Reactor Nuclear Power Plant Core Melt Scenarios with Assumed Cavity Flooding Action

Francisco Martín-Fuertes, Juan Manuel Martín-Valdepeñas, José Mira, María Jesús Sánchez

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 34-48

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3427

A Methodology for Probabilistic Accident Management

Ion Munteanu, Tunc Aldemir

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 49-62

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3428

Application of Neural Network for Loading Pattern Screening of In-Core Optimization Calculations

Akio Yamamoto

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 63-75

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3429

Dry Flowing Abrasive Decontamination Technique for Pipe Systems with Swirling Air Flow

Yutaka Kameo, Mikio Nakashima, Takakuni Hirabayashi

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 76-82

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT03-A3430

Comparative Fuel Cycle Analysis of Critical and Subcritical Fast Reactor Transmutation Systems

Edward A. Hoffman, Weston M. Stacey

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 83-106

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3431

Uncertainty Analysis on Fission Molybdenum Production with a Nuclear Fuel Target in a Research Reactor

Dong-Keun Cho, Myung-Hyun Kim

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 107-129

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT03-A3432

Segmented Gamma Scanning of Conditioned Radioactive Wastes: Development, Experimental Validation, and Application of an Angular Scanning Procedure for Hot-Spot Characterization

Alessandro Dodaro, Franco Vittorio Frazzoli, Romolo Remetti

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 130-140

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT03-A3433

Method for Removing Gadolinium from Used Heavy Water Reactor Moderator

Edward W. Wilde, Christopher J. Berry, Mudlagiri B. Goli

Nuclear Technology / Volume 144 / Number 1 / October 2003 / Pages 141-143

Technical Note / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3434

Reliability Evaluation of Passive Systems Through Functional Reliability Assessment

Luciano Burgazzi

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 145-151

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT144-145

The Application of U-Np Fuel and ⁶Li Burnable Poison for Space Reactors

Konstantin L. Nikitin, Masaki Saito, Vladimir V. Artisyuk

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 152-157

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3436

Modeling of Melt Droplet Fragmentation Following Vapor Film Destabilization by a Trigger Pulse

Eric Leclerc, Georges J. Berthoud

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 158-174

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3437

Numerical Simulation of Sodium Pool Fire

Norihiro Doda, Yasushi Okano, Hisashi Ninokata

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 175-185

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3438

Examination of Spent Pressurized Water Reactor Fuel Rods After 15 Years in Dry Storage

Robert E. Einziger, Hanchung Tsai, Michael C. Billone, Bruce A. Hilton

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 186-200

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3439

Consideration of Nuclear Criticality When Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff—I: Nuclear Criticality Constraints

Rob P. Rechard, Lawrence C. Sanchez, Holly R. Trellue

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 201-221

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-4

Consideration of Nuclear Criticality When Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff—II: Geochemical Constraints

Rob P. Rechard, Lawrence C. Sanchez, Holly R. Trellue

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 222-251

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-5

UO₂ Ceramic Grade Powders Prepared by Direct Microwave Denitration at Reduced Pressures

Daniel E. Marchi, Viviana J. Lorenzo

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 252-258

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3442

The Relationship Between Molybdenum Oxidation State and Iodine Volatility in Nuclear Fuel

S. Sunder

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 259-273

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3443

Aquaculture of Uranium in Seawater by a Fabric-Adsorbent Submerged System

Noriaki Seko, Akio Katakai, Shin Hasegawa, Masao Tamada, Noboru Kasai, Hayato Takeda, Takanobu Sugo, Kyoichi Saito

Nuclear Technology / Volume 144 / Number 2 / November 2003 / Pages 274-278

Technical Note / Miscellaneous / dx.doi.org/10.13182/NT03-2

Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants

Per F. Peterson

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 279-288

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT144-279

Molten-Salt-Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity

Charles W. Forsberg, Per F. Peterson, Paul S. Pickard

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 289-302

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-1

Criticality Calculations Using the Isopiestic Density Law of Actinide Nitrates

Nicolas P. Leclaire, Jacques A. Anno, Gérard Courtois, Pascal Dannus, Gilles Poullot, Veronique Rouyer

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 303-323

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-A3447

Numerical Analysis of Pressure Propagation and Energy Conversion Ratio in Sodium Vapor Explosions

Jie Liu, Seiichi Koshizuka, Yoshiaki Oka

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 324-336

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3448

Hazard Assessment of Fire in Electrical Cabinets

Elyahu Avidor, Francisco J. Joglar-Billoch, Frederick W. Mowrer, Mohammad Modarres

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 337-357

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3449

Effect of Entrainment and Overflow Occurrences on Concentration Profile in PUREX Flow Sheet

Yoshinori Ueda, Junichi Ishii, Shiro Matsumoto

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 358-368

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT03-A3450

Swelling and Mechanical Property Changes in Russian and American Austenitic Steels in EBR-II and BN350

Fatma Yilmaz, Yassin A. Hassan, Douglas L. Porter, Oleg Romanenko

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 369-378

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3451

Improved Application of Local Models to Steel Corrosion in Lead-Bismuth Loops

Jinsuo Zhang, Ning Li

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 379-387

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3452

Theoretical Adiabatic Temperature and Chemical Composition of Sodium Combustion Flame

Yasushi Okano, Akira Yamaguchi

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 388-399

Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT03-A3453

Algebraic Equation for Solvent Extraction Flow Sheet Under Existence of Abnormal Flows

Yoshinori Ueda, Shiro Matsumoto

Nuclear Technology / Volume 144 / Number 3 / December 2003 / Pages 400-406

Technical Note / Reprocessing / dx.doi.org/10.13182/NT03-A3454