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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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 Problems in the Design of Magnetically Confined Plasma Fusion Reactors
A. P. Fraas
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 10-19
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16270
Radiation Damage Limitations in the Design of the Wisconsin Tokamak Fusion Reactor
G. L. Kulcinski, R. G. Brown, R. G. Lott, P. A. Sanger
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 20-35
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16271
The Relevance of Various Neutron Sources to Fusion-Reactor Radiation Effects
C.M. Logan, J. D. Anderson, Z. A. Munir
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 36-44
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16272
Impurity Redistribution Around Voids in lon-Bombarded Vanadium
P. R. Okamoto, A. T. Santhanam, H. Wiedersich, A. Taylor
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 45-51
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16273
Stability of the Defect State in Neutron-Irradiated Molybdenum
V. K. Sikka, J. Moteff
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 52-65
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16274
TEM Investigation of 14-MeV Neutron Damage
K. L. Merkle
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 66-78
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16275
Effect of Helium on the Fatigue Behavior of the Molybdenum-Base Alloy TZM at 900°C
D.J. Michel, C. Z. Serpan, Jr., H. H. Smith, A. G. Pieper
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 79-87
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16276
Thermal and Electrical Conductivities and Seebeck Coefficients of Unirradiated and Irradiated Graphites from 300 to 1000°K
J. P. Moore, R. S. Graves, D. L. McElroy
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 88-93
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16277
Thermal Conductivity of Oriented Fibrous Carbon Insulation from 300 to 1300°K in Nitrogen and Argon at One Atmosphere
T. G. Godfrey, D. L. McElroy, Z. L. Ardary
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 94-107
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16278
Effects of Neutron Irradiation on the Superconducting Properties of NbTi and Nb3Sn Multifilamentary Composites
Don M. Parkin, Donald G. Schweitzer
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 108-114
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16279
Preliminary Assessment of Corrosion Product Transport in Fusion Reactors
A. B. Johnson, Jr., W. F. Vogelsang
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 115-119
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16280
Fused-Salt Corrosion and Its Control in Fusion Reactors
S. Cantor, W. R. Grimes
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 120-126
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16281
The Permeation of Hydrogen Isotopes Through Structural Metals at Low Pressures and Through Metals with Oxide Film Barriers
R. A. Strehlow, H. C. Savage
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 127-137
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16282
Effectiveness of Tritium Removal from a CTR Lithium Blanket by Cold Trapping Secondary Liquid Metals Na, K, and NaK
K. Natesan, D. L. Smith
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 138-150
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16283
The Elements of Nuclear Power
Rocco A. Fazzolare
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Page 151
Department | Fusion Reactor Materials / Book Review | doi.org/10.13182/NT74-A16284
Siting Considerations for Future Offshore Nuclear Energy Stations
Otto H. Klepper, Truman D. Anderson
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 160-169
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31399
Atlantic Generating Station
Joseph A. Ashworth
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 170-183
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT22-170
Possible Effects of Ionizing Radiation upon Marine Life and Some Implications of Postulated Accidental Releases of Radioactivity
A. F. Moscati, R. C. Erdmann
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 184-190
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31401
Natural Convection Cooling for Offshore Nuclear Power Plants
Chester D. Kylstra
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 191-195
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31402
Container Ships: Oil Fueled Versus Nuclear Powered
Thomas B. Dade, Warren F. Witzig
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 196-223
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31403
Reactor Power Plant for Undersea Applications
Robert I. Brasier, Carroll B. Mills
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 224-228
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31404
Some Characteristics of Radioisotope Power Sources in an Ocean Environment
R. C. Erdmann, E. C. Gritton, M. J. Ozeroff
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 229-236
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31405
Compact Reactor Power Systems
J. E. Brunings, D. G. Mason, W. B. Thomson, J. H. Van Osdol
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 237-251
Technical Paper | Ocean—Nuclear Energy | doi.org/10.13182/NT74-A31406
Damping of Xenon Oscillations in the Maine Yankee Reactor
W. R. Corcoran, J. R. Humphries, H. J. Litke, J. D. LeBlanc
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 252-262
Reactor | doi.org/10.13182/NT74-A31407
Minimum Critical Masses of Arrays of Fissile Oxide and Metal Elements in Water
D. C. Hunt, C. L. Schuske
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 263-274
Reactor | doi.org/10.13182/NT74-A31408
The ORNL Benchmark Experiment for Neutron Transport in Thick Sodium
R. E. Maerker, F. J. Muckenthaler, R. L. Childs
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 275-297
Shielding | doi.org/10.13182/NT74-A31409
Production of Fissioning Uranium Plasma to Approximate Gas-Core Reactor Conditions
J. H. Lee, D. R. McFarland, F. Hohl, K. H. Kim
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 306-314
Technical Paper | Reactor | doi.org/10.13182/NT74-A31415
Statistical Errors in Subcritical Reactivity Inferred from Inverse Kinetics Rod Drop Measurements Using the Three-Point Method
J. W. Allen, J. C. Robinson, N. J. Ackermann, Jr.
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 315-322
Technical Paper | Reactor | doi.org/10.13182/NT74-A31416
Inverse Kinetics Determination of Subcriticality
C. Y. Yang, R. W. Albrecht
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 323-330
Technical Paper | Reactor | doi.org/10.13182/NT74-A31417
Power Profile Manipulation in Block-Fuel HTGRs
V. Maly, E. Teuchert
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 331-334
Technical Paper | Fuel Cycle | doi.org/10.13182/NT74-A31418
Densification in Mixed Oxide Fuel During Fast Reactor Irradiation
M. C. J. Carlson
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 335-359
Technical Paper | Material | doi.org/10.13182/NT74-A31419
Laser-Controlled Thermonuclear-Reactor Materials Requirements
James M. Williams, T. G. Frank
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 360-372
Technical Paper | Material | doi.org/10.13182/NT74-A31420
Effect of Temperature on First-Wall Erosion by Radiation Blistering
M. Kaminsky, S. K. Das
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 373-378
Technical Paper | Material | doi.org/10.13182/NT74-A31421
Transmutations, Radioactivity, and Afterheat in a Deuterium-Tritium Tokamak Fusion Reactor
W. F. Vogelsang, G. L. Kulcinski, R. G. Lott, T. Y. Sung
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 379-391
Technical Paper | Material | doi.org/10.13182/NT74-A31422
Influence of Nonmetallic Impurity Elements on the Compatibility of Liquid Lithium with Potential CTR Containment Materials
D. L. Smith, K. Natesan
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 392-404
Technical Paper | Material | doi.org/10.13182/NT74-A31423
Tritium Release from Niobium
C. W. Pennington, T. S. Elleman, K. Verghese
Nuclear Technology | Volume 22 | Number 3 | June 1974 | Pages 405-415
Technical Paper | Material | doi.org/10.13182/NT74-A31424