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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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A Model of the Dynamic Behavior of the Coaxial-Flow Gaseous-Core Nuclear Reactor
Kyle H. Turner, Jr., Joseph D. Clement
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 5-14
Technical Paper | Reactor | doi.org/10.13182/NT73-A31329
On the Emission Coefficient of Uranium Plasmas
R. T. Schneider, H. D. Campbell, J. M. Mack
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 15-26
Technical Paper | Reactor | doi.org/10.13182/NT73-A31330
Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel
J. L. Straalsund, C. K. Day
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 27-34
Technical Paper | Materials | doi.org/10.13182/NT73-2
Radiation Doses from Hypothetical Exposures to Rulison Gas
C. J. Barton, R. E. Moore, S. R. Hanna
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 35-50
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT73-A31332
Effects of Gas Mixture, Electrode Spacing, Gas Pressure, and Applied Voltage on the Gamma Performance of Fission Counters
L. D. Philipp, N. C. Hoitink, W. G. Spear, M. R. Wood
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 51-59
Technical Paper | Instrument | doi.org/10.13182/NT73-A31333
Continuous Conversion of Uranium/Plutonium Nitrates to Oxides
N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 60-63
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31334
Proton Dosimeter Design for Distributed Body Organs
G. S. Khandelwal, J. W. Wilson
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 64-67
Technical Note | Instrument | doi.org/10.13182/NT73-A31335
Spectral Analysis of Sampled Nuclear Reactor Plant Data with Heterodyne Digital Filtering Techniques
H. Roggenbauer, W. Seifritz, T. Lindmo
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 79-85
Technical Paper | Reactor | doi.org/10.13182/NT73-A31343
Determination of Optimum Fuel Loadings in Pressurized Water Reactors Using Dynamic Programming
Richard B. Stout, Alan H. Robinson
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 86-102
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31344
UO2 Pellet-Stack Shortening in a Boiling Water Reactor
F. List, P. Knudsen
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 103-108
Technical Paper | Fuel | doi.org/10.13182/NT73-A31345
Use of Metallic Thorium for LWBRs and LWRs
G. B. Zorzoli
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 109-113
Technical Paper | Fuel | doi.org/10.13182/NT73-A31346
First Report on Apparatus to Simulate In-Reactor Transient Heating Conditions in Oxide Fuel Columns
B. J. Wrona, J. T. A. Roberts, E. Johanson, W. D. Tuohig
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 114-123
Technical Paper | Fuel | doi.org/10.13182/NT73-A31347
Californium-252 Assay System for FBR-Type Fuel Pins
H. O. Menlove, R. A. Forster, J. L. Parker, Darryl B. Smith
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 124-133
Technical Paper | Analysis | doi.org/10.13182/NT73-A31348
Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels
J. F. Bates, M. M. Paxton, J. L. Straalsund
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 134-135
Technical Note | Material | doi.org/10.13182/NT73-A31349
Nuclear Power Plant Heat Rejection in an Arid Climate
Frederic C. Scofield, Rocco A. Fazzolare
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 140-148
Technical Paper | Reactor | doi.org/10.13182/NT73-A31353
Methods for Calculating Vapor and Fuel Transport to the Secondary Containment in an LMFBR Accident
M. F. Kennedy, A. B. Reynolds
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 149-160
Technical Paper | Reactor | doi.org/10.13182/NT73-A31354
A Review of Fusion-Fission (Hybrid) Concepts
B. R. Leonard, Jr.,
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 161-178
Technical Paper | Reactors | doi.org/10.13182/NT73-1
Storage Capacity for Fissile Material as a Function of Facility Size
C. L. Schuske, S. J. Altschuler
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 179-189
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31356
Oxygen Interactions Between Sodium and Uranium-Plutonium Oxide Fuel
D. L. Smith
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 190-199
Technical Paper | Fuel | doi.org/10.13182/NT73-A31357
A High-Capacity Annular Centrifugal Contactor
G. J. Bernstein, D. E. Grosvenor, J. F. Lenc, N. M. Levitz
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 200-202
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31358
