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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
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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Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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Thermal Analysis of the Pennsylvania State University Breazeale Nuclear Reactor
J. A. Haag, S. H. Levine
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 6-15
Technical Paper | Reactor | doi.org/10.13182/NT73-A31313
Criticality Safety Evaluation of a Shipping Container for Moderated Low-Enriched Uranium Compounds
Ricardo Artigas
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 16-20
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31314
Thermal Considerations and Analysis for a Radioactive Waste Repository
R. D. Cheverton, W. D. Turner
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 21-33
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31315
Compatibility of Refractory Metals with 244Cm2O3
J. R. DiStefano, K. H. Lin
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 34-45
Technical Paper | Material | doi.org/10.13182/NT73-A31316
Monitoring and Measurement of Carbon Activity in Sodium Systems
K. Natesan, T. F. Kassner
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 46-57
Technical Paper | Material | doi.org/10.13182/NT73-A31317
A Dual-Energy Method for Measuring Void Fractions in Flowing Mediums
F. E. LeVert, E. Helminski
Nuclear Technology | Volume 19 | Number 1 | July 1973 | Pages 58-60
Technical Note | Instrument | doi.org/10.13182/NT73-A31318
Temperature-Dependent k∞ for a ThO2-PuO2 HTGR Lattice
Darrell F. Newman
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 66-83
Technical Paper | Reactor | doi.org/10.13182/NT73-A31322
Models for the Safe Storage of Dry and Wet Fissile Oxides
C. L. Schuske, S. J. Altschuler
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 84-95
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31323
Venting Device for Sodium-Cooled Fast Reactor Ceramic Fuel Elements
M. Martini, A. Gerosa
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 96-110
Technical Paper | Fuel | doi.org/10.13182/NT73-A31324
A Model for the Embrittlement and Annealing of Irradiated Steel
Paul J. De Meester
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 111-116
Technical Paper | Material | doi.org/10.13182/NT73-A31325
Improved Technology for Multiwatt Radioisotope Heater Units
A. W. Barsell, R. B. Goranson, P. R. Clements
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 117-125
Technical Paper | Aerospace | doi.org/10.13182/NT73-A31326
The Effect of Noncondensables on the Rate of Sodium Vapor Condensation from A Single-Rising HCDA Bubble
T. G. Theofanous, H. K. Fauske
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 132-139
Technical Paper | Reactor | doi.org/10.13182/NT73-A15874
Purification of Beryllium by Solvent Extraction from Carbonate Solutions with Quaternary Alkylammonium Carbonate
Forest G. Seeley, David J. Crouse
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 140-147
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A15875
Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels
L. A. James, R. L. Knecht
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 148-155
Technical Paper | Material | doi.org/10.13182/NT73-A15876
Fuel Capsule Vent System Development for the Viking Radioisotope Thermoelectric Generator
Frederick A. Schumann
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 156-164
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A15877
Precession Damping of Solar Probes by Reradiative Forces
Philip T. Choong, Edward A. Mason
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 165-173
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A15878
FFTF Probe-Type Eddy-Current Flowmeter: Wet Versus dry Performance Evaluation in Sodium
T. J. Costello, R. L. Laubham, W. R. Miller, C. R. Smith
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 174-180
Technical Paper | Instruments | doi.org/10.13182/NT73-3
A Photoneutron Antimony-124-Beryllium System for Fissile Materials Assay
H. O. Menlove, R. A. Forster, D. L. Matthews
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 181-187
Technical Paper | Analysis | doi.org/10.13182/NT73-A15880
Track-Etch Radiography: Alpha, Proton, and Neutron
Harold Berger
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 188-198
Technical Paper | Analysis | doi.org/10.13182/NT73-A15881
Assay of Light Water Reactor Rods for Their Uranium-235 Content
K. Böhnel
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 199-201
Technical Paper | Analysis | doi.org/10.13182/NT73-A15882
Neutron Yield from a Small High Purity 238PuO2 Source
J. K. Bair, H. M. Butler
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 202-203
Technical Note | Radioisotope | doi.org/10.13182/NT73-A15883
An In-Reactor Temperature Monitor
G. L. Hofman
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 204-206
Technical Note | Instrument | doi.org/10.13182/NT73-A15884
