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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
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Uranium-Plutonium Carbide Fuel for Fast Breeder Reactors
R. Bruce Matthews, Richard J. Herbst
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 9-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33299
General Formulation of an HCDA Bubble Rising in a Sodium Pool and the Effect of Nonequilibrium on Fuel Transport
G. Kocamustafaogullari, S. H. Chan
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 23-39
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33300
Three-Dimensional Numerical Analysis of Natural Convection of Compacted Spent Fuel
James M. Wu, Chun-Fa Chuang
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 40-49
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33301
Controlled Biaxial Strain-Rate Testing of 20% Cold-Worked Type 316 Stainless Steel Fast Reactor Cladding
N. Scott Cannon, Gary L. Wire
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 50-62
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33302
Fuel-Cladding Mechanical Interaction in PCI-Resistant LWR Fuel Designs During Normal Operation and Power Ramping
John O. Barner, Richard J. Guenther, Maxwell D. Freshley, Carl E. Crouthamel
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 63-81
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33303
Development of a Leach Model for a Commercial Nuclear Waste Glass
William L. Kuhn, Richard D. Peters, Scott A. Simonson
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 82-89
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33304
Decommissioning of Large Nuclear Power Plants with LWRs in the Federal Republic of Germany
Gerhard V. P. Watzel, Ingolf Auler
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 90-101
Technical Paper | Economic | doi.org/10.13182/NT83-A33305
Nuclear Component Wear Measurements
Keith F. Dufrane, Michael D. Naughton
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 102-109
Technical Paper | Material | doi.org/10.13182/NT83-A33306
Oxidation and Radiation Buildup on Stainless Steel Components of Boiling Water Reactors
G. Romeo
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 110-120
Technical Paper | Material | doi.org/10.13182/NT83-A33307
Resolving Power of Dynamic Radiation Gauges
Amos Notea, Yitzhak Segal
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 121-128
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT83-A33308
Summary of Denting Mechanism and Kinetic Studies with Seawater
Jean-Louis Campan, Gérard Pinard-Legry, Alain J. Vignes
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 129-150
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33309
Low-Pressure Transient Flow Film Boiling in Vertically Oriented Rod Bundles
Guy G. Loomis, Rex W. Shumway
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 151-163
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33310
Development of a Shielded Ion Microprobe Analyzer (SIMA) and Its Application to Fast Reactor Fuel Elements
Yuji Enokido, Sadamu Yamanouchi, Junji Komatsu, Toshiyuki Itaki
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 164-169
Technical Paper | Technique | doi.org/10.13182/NT83-A33311
Unfolding Triga Reactor Neutron Spectra from Multicomponent Activation Detector Data with LOUHI82
J. V. Sandberg, J. T. Routti
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 170-175
Technical Paper | Technique | doi.org/10.13182/NT83-A33312
Relative Worth of 233U and 235U in Light Water Reactor Fuel Cycles
Ansar Parvez, Martin Becker
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 176-179
Technical Note | Fuel Cycle | doi.org/10.13182/NT83-A33313
Radiative Heat Transfer in a Pressurized Water Reactor Fuel Bundle Under Accident Conditions
Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 180-184
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33314
Experimental Studies on the Use of Liquid Lead in a Molten Salt Nuclear Reactor
M. Broc, J. Sannier, G. Santarini
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 197-208
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33280
The Nuclear Reactor Strategy Between Fast Breeder Reactors and Advanced Pressurized Water Reactors
Walter Seifritz
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 209-214
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33281
An Axially Heterogeneous Core Concept for Large LMFBRs and Its HCDA Behavior
Kotaro Inoue, Kazuo Azekura, Katsuyuki Kawashima, Setsuo Kobayashi, Yoshio Watari
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 215-227
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33282
Commercial Nuclear Fuel Reprocessing Applying the SAFAR Processing Concept
Milton H. Campbell, R. E. Tomlinson, Roy Nilson, R. F. Williams
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 228-243
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33283
Operability and Maintainability of the Barnwell Nuclear Fuel Plant: A Key Issue
Robert E. Brooksbank, Sr., Ray O. Sandberg
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 244-253
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33284
Postirradiation Behavior of UO2 Fuel I: Elements at 220 to 250°C in Air
J. Novak, Ian J. Hastings, Elio Mizzan, Real J. Chenier
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 254-265
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33285
The Reduction of Neptunium(VI) by Basalt and Olivine
Nicholas J. Susak, Arnold Friedman, Sherman Fried, J. C. Sullivan
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 266-270
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33286
Electrodecontamination of Glove-Box Materials
Everett L. Childs, John R. Winkel
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 271-285
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33287
The Nuclear Reactor Strategy Between Light Water Reactors and Advanced Pressurized Water Reactors
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 286-294
Technical Paper | Economic | doi.org/10.13182/NT83-A33288
A New Postirradiation Mechanical Behavior Test—The Miniaturized Disk Bend Test
Michael P. Manahan
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 295-315
Technical Paper | Material | doi.org/10.13182/NT83-A33289
Heat Removal Tests for Pressurized Water Reactor Containment Spray by Large-Scale Facility
Yasuo Motoki, Mitsuo Naritomi, Mitsugu Tanaka, Gunji Nishio, Kazuichiro Hashimoto, Susumu Kitani
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 316-329
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33290
SIMMER-II Recriticality Analyses for a Homogeneous Core of the 300-MW(electric) Class
Werner Maschek, Margaret W. Asprey
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 330-336
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33291
The Noncondensable Gas Effects on Loss-of-Coolant Accident Steam Condensation Loads in Boiling Water Reactor Pressure Suppression Pool
Yutaka Kukita, Ken Namatame, Isao Takeshita, Masayoshi Shiba
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 337-346
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33292
Nuclear Criticality Safety Considerations in Design of Dry Fuel Assembly Storage Arrays
Edward T. Tomlinson, C. L. Brown
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 347-350
Technical Note | Nuclear Safety | doi.org/10.13182/NT83-A33293
Physics of a Gaseous Core Reactor
Hugo Van Dam, J. Eduard Hoogenboom
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 359-368
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33265
An Assessment of the Core Degradation Frequency in a Typical Large LMFBR Design for Internal Accident Initiators—A Comparison with PWR Predictions
Constantine P. Tzanos, Nelson A. Hanan, Achilles G. Adamantiades
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 369-396
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33266
Performance Characteristics of the Annular Core Research Reactor Fuel Motion Detection System
J. G. Kelly, K. T. Stalker
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 397-414
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33267
Iterative Solution to the Optimal Poison Management Problem in Pressurized Water Reactors
J. P. Colletti, Samuel H. Levine, John B. Lewis
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 415-425
Technical Paper | Fuel Cycle | doi.org/10.13182/NT83-A33268
The Possibility for Spark-Initiated Explosion in Mixtures of Uranium Hexafluoride and Deuterium
Jon L. Maienschein
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 426-430
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33269
Oxidation of Pu(III) by Nitric Acid in Tri-n-Butyl Phosphate Solutions. Part II. Chemical Methods for the Suppression of Oxidation to Improve Plutonium Separation in Contactor Operation
Yu-Keung Sze, Joseph Alfred Gosselin
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 431-441
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33270
The Sodium-Bonding Pin Concept for Advanced Fuels Part I: Swelling of Carbide Fuel up to 12% Burnup
Michel Colin, Michel Coquerelle, Ian L. F. Ray, Claudio Ronchi, Clive T. Walker, Hubert Blank
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 442-460
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33271
Radionuclide Analyses Taken During Primary Coolant Decontamination at Three Mile Island Indicate General Circulation
Kenneth J. Hofstetter, C. G. Hitz, V. F. Baston, Anthony P. Malinauskas
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 461-469
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33272
Leaching of 137Cs, 134Cs, and 129I from Irradiated UO2 Fuel
L. H. Johnson, K. I. Burns, H. H. Joling, C. J. Moore
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 470-475
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33273
Materials for High-Level Waste Canister/Overpacks in Salt Formations
Martin A. Molecke, James A. Ruppen, Ronald B. Diegle
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 476-506
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33274