ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
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?
Jump to:
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
