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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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NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
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A Probabilistic Methodology to Determine Failure Probabilities and Acceptance Criteria for the KBS-3 Inserts Under Ice-Age Load Conditions
Karl-Fredrik Nilsson, Peter Dillström, Claes-Göran Andersson, Fred Nilsson, Mats Andersson, Philip Minnebo, Lars-Erik Bjorkegren, Bo Erixon
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 3-14
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3964
Factors Affecting Risk Predictions: Can Some Risk Metrics Be More Accurately Predicted Than Others?
Robert W. Rice, John C. Walton
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 15-23
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3965
Assessing Effects of Thermal Loading on the Stability of Emplacement Drifts
G. I. Ofoegbu, K. J. Smart, B. Dasgupta
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 24-30
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3966
An Analysis of External Radiation Dose Fields in an Underground Facility at the Potential HLW Geologic Repository at Yucca Mountain, Nevada
Oleg G. Povetko
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 31-37
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3967
Double-Diffusive Natural Convection in a Nuclear Waste Repository
Yue Hao, John J. Nitao, Thomas A. Buscheck, Yunwei Sun
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 38-46
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3968
Increased Storage Capacity at Yucca Mountain Favors Thermal Management for a Cold Repository
G. Danko, J. Walton, D. Bahrami
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 47-61
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3969
Modeling Temperature Distribution Around Very Deep Borehole Disposals of HLW
Fergus G. F. Gibb, Karl P. Travis, Neil A. McTaggart, David Burley, Kevin W. Hesketh
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 62-73
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3970
Impact of Advanced Fuel Cycles on Geological Disposal in a Clay Formation
Jan Marivoet, Eef Weetjens
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 74-84
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3971
Independent Evaluation of Waste Package Corrosion Performance Under Potential Repository Conditions
Y.-M. Pan, K. T. Chiang, D. S. Dunn, X. He, O. Pensado, P. Shukla, L. Yang
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 85-91
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3972
Implementation of Localized Corrosion in the Performance Assessment Model for Yucca Mountain
S. David Sevougian, Vivek Jain, Robert J. MacKinnon, Patrick D. Mattie, Kevin G. Mon, Bryan E. Bullard
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 92-100
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3973
Results from an International Simulation Study on Coupled Thermal, Hydrological, and Mechanical Processes near Geological Nuclear Waste Repositories
J. Rutqvist, D. Barr, J. T. Birkholzer, M. Chijimatsu, O. Kolditz, Quansheng Liu, Y. Oda, Wenqing Wang, Chengyuan Zhang
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 101-109
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3974
Coupled In-Rock and In-Drift Hydrothermal Model Study for Yucca Mountain
G. Danko, J. Birkholzer, D. Bahrami
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 110-128
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3975
Time-Domain Random-Walk Algorithms for Simulating Radionuclide Transport in Fractured Porous Rock
Scott L. Painter, Vladimir Cvetkovic, Osvaldo Pensado
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 129-136
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3976
Formulation of Time-Domain Random-Walk Compartment Model for Radionuclide Migration from a Geologic Repository
Daisuke Kawasaki, Joonhong Ahn
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 137-146
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3977
A Modeling Study Evaluating the Thermal-Hydrological Conditions in and near Waste Emplacement Drifts at Yucca Mountain
J. T. Birkholzer, N. Halecky, S. W. Webb, P. F. Peterson, G. S. Bodvarsson
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 147-164
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3978
Impact of Landscape Topography and Quaternary Overburden on the Performance of a Geological Repository of Nuclear Waste
Lars Marklund, Anders Wörman, Joel Geier, Eva Simic, Björn Dverstorp
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 165-179
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3979
Probabilistic Methodology for Long-Term Assessment of Volcanic Hazards
Olivier Jaquet, Charles Connor, Laura Connor
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 180-189
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3980
Risk-Informed Design Changes in a Passive Decay Heat Removal System
Giovanbattista Patalano, George E. Apostolakis, Pavel Hejzlar
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 191-208
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3981
Validation of Severe Accident Codes on the Phebus Fission Product Tests in the Framework of the PHEBEN-2 Project
K. Mueller, S. Dickinson, C. de Pascale, N. Girault, L. Herranz, F. De Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuertes, I. Turcu, I. Ivanov, B. Toth, G. Horvath
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 209-227
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3982
Aerosol Studies in a Nuclear Aerosol Test Facility Under Different Turbulence Conditions
B. K. Sapra, Y. S. Mayya, Arshad Khan, Faby Sunny, Sunil Ganju, H. S. Kushwaha
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 228-244
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3983
Quantum-Chemical Calculations of the Equilibrium Constants of a Fission Product Mixture in a Steam-Hydrogen Carrier Gas in Severe Accident Conditions
Jan Machacek, Laurent Cantrel, Peter Kluvanek, Marek Liska, Ondrej Gedeon
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 245-251
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3984
Behavior of a Defective Nuclear Fuel Rod in Dry Storage Conditions Studied with a New Experimental Setup
L. Desgranges, M. P. Ferroud-Plattet, R. Alloncle, I. Aubrun, J. M. Untrau, P. Lhuillery
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 252-260
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3985
Analysis of Steam Condensation Heat Transfer with a Noncondensable Gas in a Vertical Condenser Tube
Kwon-Yeong Lee, Moo Hwan Kim
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 261-272
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3986
COBRA-TF Analysis of the High Flux Reactor Hot Channel for a Postulated Large-Break Loss-of-Coolant Accident
Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 273-284
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3987
Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - I: Two-Layer System Mass Transfer Theory
Michael Epstein, Hans K. Fauske, Charles F. Askonas, Marc A. Vial, Patricia Paviet-Hartmann
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 285-293
Technical Paper | Reprocessing | doi.org/10.13182/NT08-A3988
Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - II: Experimental Data on Reaction Self-Heat Rates and Gas Production and Their Correlation
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 294-306
Technical Paper | Reprocessing | doi.org/10.13182/NT08-A3989
Thermal Stability and Safe Venting of the Tri-N-Butyl Phosphate-Nitric Acid-Water ("Red Oil") System - III: Predictions of Thermal Stability Boundaries and Required Vent Size
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 307-320
Technical Paper | Reprocessing | doi.org/10.13182/NT08-A3990
Production of High-Density Uranium Carbide Compacts for Use in Composite Nuclear Fuels
Gokul Vasudevamurthy, Travis W. Knight
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 321-327
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A3991
Evaluation of Salt Coolants for Reactor Applications
D. F. Williams, K. T. Clarno
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 330-343
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT08-A3992
Options for Scaled Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Convective Heat Transfer
Philippe M. Bardet, Per F. Peterson
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 344-357
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT163-344
Influence of the Processing and Salt Composition on the Thorium Molten Salt Reactor
Elsa Merle-Lucotte, Ludovic Mathieu, Daniel Heuer, Véronique Ghetta, Roger Brissot, Christian Le Brun, Eric Liatard
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 358-365
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT08-A3994
Electrodeposition of Uranium and Transuranics Metals (Pu) on Solid Cathode
A. F. Laplace, J. Lacquement, J. L. Willit, R. A. Finch, G. A. Fletcher, M. A. Williamson
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 366-372
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT08-A3995
Electrochemical Determination of Gadolinium and Plutonium Solvation Properties in Liquid Gallium at High Temperature
Sylvie Delpech, Gérard Picard, Jörgen Finne, Eric Walle, Olivier Conocar, Annabelle Laplace, Jérôme Lacquement
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 373-381
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT08-A3996
A New Technology for the Nuclear Industry for the Complete and Continuous Pyrochemical Reprocessing of Spent Nuclear Fuel: Catalyst Enhanced Molten Salt Oxidation
Trevor R. Griffiths, Vladimir A. Volkovich
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 382-400
Technical Paper | Molten Salt Chemistry and Technology | doi.org/10.13182/NT08-A3997
A Study of Air Ingress and Its Prevention in HTGR
Xing L. Yan, Tetsuaki Takeda, Tetsuo Nishihara, Kazutaka Ohashi, Kazuhiko Kunitomi, Nobumasa Tsuji
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 401-415
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A3998
Finite Element Modeling of Thermal-Mechanical Behaviors of Dispersion Fuel Elements
Shurong Ding, Yongzhong Huo
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 416-425
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3999
A Comparison of Experimental Results and FLUENT Simulations for Void-Fraction Distribution in a Two-Phase System
R. Saksena, P. Satyamurthy, P. Munshi
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 426-434
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A4000
An Advanced Boiling Water Reactor Monitoring System Using Modular Accident Analysis Program and Computer Graphical User Interface
Yuan-Hsiang Chang, Mu-Ping Xu, Jyh-Tong Teng, Te-Chuan Wang, Ray-Feng Chiang, Huey-Ling Hwu, Wang-Chyuan Chen
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 435-443
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT08-A4001
A Novel Approach to Spent Fuel Pool Decommissioning
R. L. Demmer, J. B. Panozzo, R. J. Christensen
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 444-452
Technical Paper | Decontamination/decommissioning | doi.org/10.13182/NT08-A4002