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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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The uranium market closed out 2024 with a spot price of $72.63 per pound and a long-term price of $80.50 per pound, according to global uranium provider Cameco.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT03-4
Consideration of Nuclear Criticality When Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff—II: Geochemical Constraints
Nuclear Technology | Volume 144 | Number 2 | November 2003 | Pages 222-251
Technical Paper | Radioactive Waste Management and Disposal | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT03-A3454
