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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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May 2025
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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Boiling Water Reactor Control Rod Programming Using Heuristic and Mathematical Methods
Tamotsu Hayase, Hiroshi Motoda
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 91-100
Technical Paper | Reactor | doi.org/10.13182/NT80-A32455
A Radionuclide Trap for Liquid-Metal-Cooled Reactors
J. C. McGuire, W. F. Brehm
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 101-109
Technical Paper | Reactor | doi.org/10.13182/NT80-A32456
Reaction Rate Calculations in Uranium and Thorium Blankets Surrounding a Central Deuterium-Tritium Neutron Source
A. D. Krumbein, M. Lemanska, M. Segev, J. J. Wagschal, A. Yaari
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 110-116
Technical Paper | Reactor | doi.org/10.13182/NT80-A32457
Rotating Plug Size Study for Liquid-Metal Fast Breeder Reactors
L. J. Nemeth
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 117-121
Technical Paper | Reactor | doi.org/10.13182/NT80-A32458
Experimental Value of Percent Variation in Root-Mean-Square Ex-Core Detector Signal to the Core Barrel Amplitude Scale Factor
J. P. Thompson, G. R. McCoy, B. T. Lubin
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 122-127
Technical Paper | Reactor | doi.org/10.13182/NT80-A32459
Critical Experiments with Solid Neutron Absorbers and Water-Moderated Fast Test Reactor Fuel Pins
B. M. Durst, S. R. Bierman, E. D. Clayton, J. F. Mincey
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 128-149
Technical Paper | Fuel | doi.org/10.13182/NT80-A32460
Remodeling and Dosimetry on the Neutron Irradiation Facility of the Musashi Institute of Technology Reactor for Boron Neutron Capture Therapy
Otohiko Aizawa, Keiji Kanda, Tetsuya Nozaki, Tetsuo Matsumoto
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 150-163
Technical Paper | Radiation | doi.org/10.13182/NT80-A32461
Subcritical Limits for Special Fissile Actinides
H. K. Clark
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 164-170
Technical Paper | Analysis | doi.org/10.13182/NT80-A32462
Effects of Indoor Residence on Radiation Doses from Routine Releases of Radionuclides to the Atmosphere
D. C. Kocher
Nuclear Technology | Volume 48 | Number 2 | April 1980 | Pages 171-179
Technical Note | Radioisotope | doi.org/10.13182/NT80-A32463
An Experimental Technique for Determination of Steam Fraction in Flowing Steam / Air Mixtures
N. Saba, R. T. Lahey, Jr., J. C. Corelli
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 5-15
Technical Paper | Reactor | doi.org/10.13182/NT80-A32443
Pellet and Pellet-Blanket Neutronics and Photonics for Electron Beam Fusion
Magdi M. H. Ragheb, Gregory A. Moses, Charles W. Maynard
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 16-33
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32444
Multigoal Fuel Cycle Optimization Including Nonproliferation Objectives
P. Silvennoinen, T. Vieno, J. Vira
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 34-42
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32445
Fission Gas Release and Microscopic Swelling in Highly Rated Advanced Fuels
M. Coquerelle, C. T. Walker
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 43-53
Technical Paper | Fuel | doi.org/10.13182/NT80-A32446
Reprocessing Nuclear Fuels of the Future: A Radiological Assessment of Advanced (Th,U) Carbide Fuel
J. E. Till, H. R. Meyer, L. E. Morse, W. D. Bond, E. S. Bomar, V. J. Tennery
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 54-62
Technical Paper | Fuel | doi.org/10.13182/NT80-A32447
Analysis, Critique, and Reevaluation of High-Level Waste Repository Water Intrusion Scenario Studies
Bernard L. Cohen
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 63-69
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32448
Effects of Simulated Fission Products on the Mechanical Properties of Zircaloy-2
R. Kohli, F. Holub
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 70-76
Technical Paper | Material | doi.org/10.13182/NT80-A32449
Desorption Kinetics of Methyl Iodide from Impregnated Charcoal
Leonard A. Jonas, Victor R. Deitz, J. B. Romans
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 77-83
Technical Paper | Radioisotope | doi.org/10.13182/NT80-A32450
Dose Rates from Induced Activity in the Tokamak Fusion Test Reactor Test Cell
R. G. Alsmiller, Jr., J. Barish, R. T. Santoro, R. A. Lillie, J. M. Barnes, M. M. H. Ragheb
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 187-195
Technical Paper | Reactor | doi.org/10.13182/NT80-A32466
Impurity Deposition in a Mesh-Packed Cold Trap
Michio Murase, Isao Sumida, Norio Nagase, Kazuo Mukai, Osamu Onuki
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 196-203
Technical Paper | Reactor | doi.org/10.13182/NT80-A32467
Development Studies Regarding the Construction of Epithermal-Enriched Neutron Field for Medical Purposes at the University of Tokyo YAYOI Fast Reactor
Shigehiro An, Akira Furuhashi, Yoshiaki Oka, Masatsugu Akiyama, Hiroyuki Kuga,+, Harukuni Tanaka
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 204-215
Technical Paper | Reactor | doi.org/10.13182/NT80-A32468
Nuclear Performance of Molten Salt Fusion-Fission Symbiotic Systems for Catalyzed Deuterium-Deuterium and Deuterium-Tritium Reactors
M. M. H. Ragheb, R. T. Santoro, J. M. Barnes, M. J. Saltmarsh
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 216-232
Technical Paper | Reactor | doi.org/10.13182/NT80-A32469
On the Volatilization Potential of Metallic Inclusions Found in Irradiated UO2 Fuel During Overheating Events
Paul Sasa, August W. Cronenberg+, Michael G. Stevenson
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 233-250
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32470
Supercriticality Through Optimum Moderation in Nuclear Fuel Storage
J. M. Cano, R. Caro, J. M. Martnez-Val
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 251-260
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32471
International Symbiosis: The Role of Thorium and The Breeders
D. M. Ligon, R. H. Brogli
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 261-272
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32472
Development and Performance of Metal Fuel Elements for Fast Breeder Reactors
L. C. Walters, J. H. Kittel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 273-280
Technical Paper | Fuel | doi.org/10.13182/NT80-A32473
The Effect of Low Pressurized Water Reactor Containment Pressure on Peak Cladding Temperatures
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Application of Simplified Reliability Methods for Risk Assessment of Nuclear Waste Repositories
Andreas Pritzker, Jrg Gassmann
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 289-297
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32475
Corrosion of 15 Cr—35 Ni—50 Fe Doped with Niobium, Titanium, or Molybdenum in High Temperature Reactor Helium
Otto Demel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 298-302
Technical Paper | Material | doi.org/10.13182/NT80-A32476
Empirical Development of Irradiation-Induced Swelling Design Equations
J. F. Bates, M. K. Korenko
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 303-314
Technical Paper | Material | doi.org/10.13182/NT80-A32477
