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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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Analysis of the Xenon Feedback on the Core Dynamics of High-Temperature Reactors During Heat Removal Transients Without Reactor Shutdown
Rahim Nabbi
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 5-13
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33321
Accumulation Process of Plutonium Third Phase in Mixer-Settlers
Kozo Gonda, Koichiro Oka
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 14-18
Technical Paper | Chemical Processing | doi.org/10.13182/NT84-A33322
A Conceptual Design of a Fuel Bundle for Extended Burnup in Boiling Water Reactors
Motoo Aoyama, Sadao Uchikawa, Kazuyoshi Miki, Kazuo Hiramoto, Renzo Takeda
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 19-25
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33323
A Three-Dimensional Potential Flow Model for the Prediction of the Behavior of Radioactive Plumes
Yoichi Ichikawa, Hiroshi Shikata
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 26-34
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33324
Radiation Buildup on Stainless Steel in a Boiling Water Reactor Environment
Takashi Honda, Masakiyo Izumiya, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 35-42
Technical Paper | Material | doi.org/10.13182/NT84-A33325
Accelerated One-Phase Flow Through Perforated Plates
Folco Casadei, Mario Dalle Donne+
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 43-69
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33326
Sensor Fault Analysis Using Decision Theory and Data-Driven Modeling of Pressurized Water Reactor Subsystems
Belle R. Upadhyaya, Malgorzata Skorska
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 70-77
Technical Paper | Technique | doi.org/10.13182/NT84-A33327
The Accuracy of T(d, n)4He Neutron Energy Measurements Using an NE-213 Liquid Scintillator
Alex Tsechanski, Gad Shani
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 78-87
Technical Paper | Technique | doi.org/10.13182/NT84-A33328
Selection and Benchmarking of Computer Codes for Research Reactor Core Conversions
Emin Yilmaz, Barclay G. Jones
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 88-100
Technical Note | Fission Reactor | doi.org/10.13182/NT84-A33329
General Empirical Model for 60Co Generation in Pressurized Water Reactors with Continuous Refueling
Guillermo A. Urrutia, Alberto J. G. Maroto, Roberto Fernández-Prini, Miguel A. Blesa
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 107-114
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33334
Time-Dependent Accident Sequences Including Human Actions
G. Apostolakis, T. L. Chu
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 115-126
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33335
FUMAC—A New Model for Light Water Reactor Fuel Relocation and Pellet-Cladding Interaction
Lewis A. Walton, John E. Matheson
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 127-138
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33336
Fuel/Cladding Chemical Interaction in Mixed-Oxide Fuel at High Burnup
Leo A. Lawrence
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 139-153
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33337
Numerical Analysis of Nuclide Migration Through Fissured Geological Media
Joonhong Ahn, Atsuyuki Suzuki, Ryohei Kiyose
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 154-165
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33338
Guidelines for the Selection of Sites That Might Prove Suitable for Radioactive Waste Disposal on or Beneath the Ocean Floor
R. C. Searle
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 166-174
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33339
Fracture Toughness Behavior of Unirradiated and Irradiated Cr—1 Mo Steel Plate and Weldment
W. J. MILLS
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 175-185
Technical Paper | Material | doi.org/10.13182/NT84-A33340
Turbulent Condensation on a Cold Wall in the Presence of a Noncondensable Gas
Michael L. Corradini
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 186-195
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33341
A Kinetics and Thermal-Hydraulics Capability for the Analysis of Research Reactors
William L. Woodruff
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 196-206
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33342
Development and Test of the Three-Dimensional Computer Code ZELT-3D for Unfolding Power Distributions Using Side Reflector Instrumentation Signals
Paulo J. Knob, Ralf D. Neef, Hartwig Schaal
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 217-228
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33351
An Event-Oriented Method for Determining Operation Guides Under Emergency Conditions in Boiling Water Reactors
Yukiharu Ohga, Shunsuke Utena
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 229-236
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33352
Recovery of 3%-Enriched Uranium by Means of a Chemical Method
Tetsuya Miyake, Kunihiko Takeda, Kazuo Imamura, Heiichiro Obanawa
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 237-242
Technical Paper | Chemical Processing | doi.org/10.13182/NT84-A33353
Conceptual Design of a High-Burnup Fuel Rod for Boiling Water Reactors Using Low-Density UO2 Pellets of an Annular Type
Kazuo Hiramoto, Motoo Aoyama, Masaharu Sakagami, Renzo Takeda
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 243-248
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33354
Application of Value-lmpact Methodology in the Design Analysis of a Nuclear Safety System
Michael G. Stamatelatos, Daisy M. Ligon, Achilles G. Adamantiades
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 249-267
Technical Paper | Economic | doi.org/10.13182/NT84-A33355
Dynamic Fracture Toughness of Irradiated A533 Grade B Class 1 Pressure Vessel Steel
K. Linga Murty, R. P. Shogan, W. H. Bamford
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 268-274
Technical Paper | Material | doi.org/10.13182/NT84-A33356
Experimental Studies of Penetration of a Hot Liquid Pool into a Melting Miscible Substrate
Gismar Eck, Heinrich Werle
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 275-289
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33357
Transit Time of Mixed High Pressure Injection Water and Primary Loop Water in Pressurized Water Reactor Cold Legs
Bill K.-H. Sun, Seung Oh, Paul H. Rothe
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 290-299
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33358
Tritiated Water Measurements with a 2D(γ,n)1H Detector
Willard G. Winn, Norman P. Baumann
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 300-306
Technical Paper | Technique | doi.org/10.13182/NT84-A33359