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Division Spotlight
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.
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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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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Materials Considerations in Radioactive Waste Storage
Warren K. Eister
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 6-9
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31731
Hanford Waste Encapsulation: Strontium and Cesium
R. R. Jackson
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 10-15
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31732
Stabilization and Storage of Solidified High-Level Radioactive Wastes
J. R. Berreth, A. P. Hoskins, J. A. Rindfleisch
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 16-24
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31733
Packaging Rocky Flats Waste
Charles E. Wickland
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 25-29
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31734
Some Techniques for the Solidification of Radioactive Wastes in Concrete
Peter Colombo, Robert M. Neilson, Jr.
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 30-38
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31735
Leach Behavior of Hydrofracture Grout Incorporating Radioactive Wastes
J. G. Moore, H. W. Godbee, A. H. Kibbey
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 39-52
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31736
Packaging of Tritium-Contaminated Liquid Waste
E. A. Mershad, W. W. Thomasson, J. J. Dauby
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 53-59
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31737
The Canadian Spent Fuel Storage Canister: Some Materials Aspects
Derek G. Boase, Tjalle T. Vandergraaf
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 60-71
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31738
High-Level Waste Glass
John E. Mendel
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 72-87
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31739
High-Level Waste Glass: Field Leach Test
W. F. Merritt
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 88-91
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31740
High-Level Waste Ceramics: Materials Considerations, Process Simulation, and Product Characterization
Gregory J. McCarthy
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 92-105
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31741
In Situ Regeneration of Fusion Reactor First Walls
J. Chin, T. Ohkawa
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 115-124
Technical Paper | Reactor | doi.org/10.13182/NT77-A31717
Analysis of Reactor Component Fluence Limits Using Damage Function Methods
G. R. Odette, R. L. Simons, W. N. McElroy, D. G. Doran
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 125-141
Technical Paper | Reactor | doi.org/10.13182/NT77-A31718
Toroidal Field Strength Requirements in Tokamak Reactors
W. M. Stacey, Jr., K. Evans, Jr.
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 142-154
Technical Paper | Reactor | doi.org/10.13182/NT77-A31719
Sensitivity Assessments in Reactor Safety Analysis
J. E. Kelly, F. L. Leverenz, Jr., N. J. McCormick, R. C. Erdmann
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 155-166
Technical Paper | Reactor | doi.org/10.13182/NT77-A31720
Study of the Dissolution of Refractory PuO2 in Nitric-Hydrofluoric Acid Dissolvents at 100°C
O. K. Tallent, J. C. Mailen
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 167-175
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31721
Uranium-236 in Light Water Reactor Spent Fuel Recycled to an Enriching Plant
A. de la Garza
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 176-185
Technical Paper | Fuel | doi.org/10.13182/NT77-A31722
The Reactivity Perturbation Assay of Irradiated Fuel Rods
L. Green, J. T. Kriese, M. Natelson
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 186-204
Technical Paper | Fuel | doi.org/10.13182/NT77-A31723
A Gamma-Ray Perimeter Security System
Donald A. Close
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 205-210
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A31724
Optimal Synthesis of a Power Plant Cooling System
L. T. Fan, David F. Aldis
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 222-238
Technical Paper | Reactor | doi.org/10.13182/NT77-A31747
Properties of Light Water Reactor Core Melts
S. Nazaré, G. Ondracek, B. Schulz
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 239-246
Technical Paper | Reactor | doi.org/10.13182/NT77-A31748
Reliability Analysis of the Decay Heat Removal System of a 1000-MW(e) Gas-Cooled Fast Breeder Reactor
D. Bittermann, J. Wehling
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 247-256
Technical Paper | Reactor | doi.org/10.13182/NT77-A31749
Comparison of the Power Distribution in Uranium and Plutonium Fuel Elements in the KWO Core
Dieter Sommer
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 257-275
Technical Paper | Reactor | doi.org/10.13182/NT77-A31750
Mechanical Response of UO2 Subjected to Transient Heating
B. J. Wrona, J. T. A. Roberts, T. M. Galvin, G. T. Higgins
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 276-289
Technical Paper | Fuel | doi.org/10.13182/NT77-A31751
The Overall Probability of Detection in Connection with the Optimization of Safeguards Effort
Günter Hartmann
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 290-296
Technical Paper | Material | doi.org/10.13182/NT77-A31752
Equilibrium Pressure and Solubility of Hydrogen in Liquid Lithium
Hiroji Katsuta, Takahiro Ishigai, Kazuo Furukawa
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 297-303
Technical Paper | Material | doi.org/10.13182/NT77-A31753
Sodium Purification by Cold Trapping at the Experimental Breeder Reactor II
J. T. Holmes, C. R. F. Smith, M. M. Osterhout, W. H. Olson
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 304-314
Technical Paper | Material | doi.org/10.13182/NT77-A31754
A Californium-252 Fission Spectrum Irradiation Facility for Neutron Reaction Rate Measurements
J. A. Grundl, V. Spiegel, C. M. Eisenhauer, H. T. Heaton II, D. M. Gilliam, J. Bigelow
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 315-319
Technical Paper | Radioisotope | doi.org/10.13182/NT77-A31755
The Application of SPOOL-FIRE in Theoretical Analysis and Experimental Comparison
Lucy Wu Person
Nuclear Technology | Volume 32 | Number 3 | March 1977 | Pages 320-325
Technical Note | Reactor | doi.org/10.13182/NT77-A31756