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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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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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Uranium-233 Breeding and Neutron Multiplying Blankets for Fusion Reactors
Andrew G. Cook, James A. Maniscalco
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 5-11
Technical Paper | Reactor | doi.org/10.13182/NT76-A31618
On the Use and Influence of Gamma Radiation in Reactor Noise Measurements
Bruno Bärs
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 12-23
Technical Paper | Reactor | doi.org/10.13182/NT76-A31619
The Development of an Environmental Monitoring System for the Continuous Detection of Low-Level Radioactive Gases
R. H. Jabs, W. A. Jester
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 24-32
Technical Paper | Reactor Siting | doi.org/10.13182/NT76-A31620
Technological Development Concerning the Gas-Cooled Fast Breeder Reactor Test Bundle for the Irradiation Test in the Helium Loop at Mol
M. Peehs, P. Rau
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 33-46
Technical Paper | Fuel | doi.org/10.13182/NT76-A31621
Procedure for Determining Leachabilities of Radioactive Waste Forms
J. A. Kelley, R. M. Wallace
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 47-51
Technical Paper | Radioactive Waste | doi.org/10.13182/NT76-A31622
Interrelationships Between Creep Life Criteria for Four Nuclear Structural Materials
M. K. Booker, V. K. Sikka
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 52-64
Technical Paper | Material | doi.org/10.13182/NT76-A31623
Radiative Heat Transfer in Molten UO2 Based on the Rosseland Diffusion Method
Edward E. Anderson
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 65-70
Technical Paper | Material | doi.org/10.13182/NT76-A31624
A Simple Method for Calculations of Steady-State Creep Rates in Nonconservative Plastic Deformation
G. L. Wire, J. L. Straalsund
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 71-76
Technical Paper | Material | doi.org/10.13182/NT76-A31625
Instrumented Fast-Reactor Irradiation of Boron Carbide Pellets
A. L. Pitner
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 77-85
Technical Paper | Material | doi.org/10.13182/NT76-A31626
Volume Reduction of Plutonium-Contaminated Soil
J. H. Horton, E. L. Albenesius
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 86-88
Technical Note | Radioactive Waste | doi.org/10.13182/NT76-A31627
History of Fissile Array Measurements in the United States
C. L. Schuske, Hugh C. Paxton
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 101-137
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31612
A Review of Criticality Safety Models Used in Evaluating Arrays of Fissile Materials
Douglas C. Hunt
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 138-165
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31613
The Monte Carlo Method for Array Criticality Calculations
Deanne Dickinson, G. Elliott Whitesides
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 166-189
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31614
Comparative Calculational Evaluation of Array Criticality Models
Douglas C. Hunt, Deanne Dickinson
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 190-214
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31615
Uranium Resources—Are they Adequate?
Robert D. Nininger
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 224-231
Technical Paper | Uranium Resource / Fuel Cycle | doi.org/10.13182/NT76-A31638
U3O8 Supply in Technical and Commercial Transition
P. F. Schutt, J. S. Hobbs
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 232-236
Technical Paper | Uranium Resource / Fuel Cycle | doi.org/10.13182/NT76-A31639
The Changing Scene for Uranium in Canada
Noel O’Brien
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 237-241
Technical Paper | Uranium Resource / Fuel Cycle | doi.org/10.13182/NT76-A31640
Uranium: The Market and Adequacy of Supply
Bernard H. Cherry
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 242-245
Technical Paper | Uranium Resource / Fuel Cycle | doi.org/10.13182/NT76-A31641
Transient Hydraulics and Heat Transfer in Turbulent Flow
Hiroshi Kawamura
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 246-255
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31642
Safety Advantages of Prestressed Concrete Reactor Vessels
Zdeněk P. Bažant
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 256-260
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31643
A Tokamak Experimental Power Reactor
W. M. Stacey, Jr., V. A. Maroni, J. R. Purcell, M. A. Abdou, P. J. Bertoncini, J. N. Brooks, J. B. Darby, Jr., K. Evans, Jr., J. A. Fasolo, R. L. Kustom, J. S. Moenich, J. S. Patten, D. L. Smith, H. C. Stevens, S. T. Wang
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 261-298
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31644
Theoretical and Experimental Dynamic Analysis of the H. B. Robinson Nuclear Plant
T. W. Kerlin, E.M. Katz, J. G. Thakkar, J. E. Strange
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 299-316
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31645
Removal of Radioiodine from Gas Streams by Electrolytic Scrubbing
J. C. Mailen, D. E. Horner
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 317-324
Technical Paper | Uranium Resource / Chemical Processing | doi.org/10.13182/NT76-A31646
Use of Chemical Equilibrium Data to Calculate Iodox Column Operations
J. C. Mailen
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 325-332
Technical Paper | Uranium Resource / Chemical Processing | doi.org/10.13182/NT76-A31647
Velocity Measurements in the Subchannel of the Wire-Spaced Subassembly
Toshihide Ohtake, Shinichi Uruwashi, Keiichi Takahashi
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 333-349
Technical Paper | Uranium Resource / Fuel | doi.org/10.13182/NT76-A31648
Neutron Spectrum and Radial Power Distribution Measurements in a TRIGA Reactor Fuel Element
Walter L. Weaver III, Marvin E. Wyman, Barclay G. Jones
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 350-360
Technical Paper | Uranium Resource / Fuel | doi.org/10.13182/NT76-A31649
Cladding Ovalities in Advanced Liquid-Metal Fast Breeder Reactor Fuel Elements
Jerry F. Kerrisk, John O. Barner, Roy L. Petty
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 361-375
Technical Paper | Uranium Resource / Fuel | doi.org/10.13182/NT76-A31650
Swelling and Microstructural Changes in Irradiated Vanadium Alloys
J. Bentley, F. W. Wiffen
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 376-384
Technical Paper | Uranium Resource / Material | doi.org/10.13182/NT76-A31651
Grain Boundary Penetration Kinetics of Nitrided Type 304L Stainless Steel
J. A. Reeves, Jr., D. L. Olson, W. L. Bradley
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 385-389
Technical Paper | Uranium Resource / Material | doi.org/10.13182/NT76-A31652
Influence of Section Thickness on Fatigue Crack Growth in Type 304 Stainless Steel
Paul Shahinian
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 390-397
Technical Paper | Uranium Resource / Material | doi.org/10.13182/NT76-A31653
Fast-Neutron Hodoscope at TREAT: Data Processing, Analysis, and Results
A. De Volpi, R. R. Stewart, J. P. Regis, G. S. Stanford, E. A. Rhodes
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 398-421
Technical Paper | Uranium Resource / Instrument | doi.org/10.13182/NT76-A31654
Evaluation of Initial Loading Counting Rate Data from Experiments with the Mock-Up Core for the Fast Flux Test Facility
J. T. Mihalczo, G. C. Tillett, D. L. Selby
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 422-433
Technical Paper | Uranium Resource / Instrument | doi.org/10.13182/NT76-A31655
Neutron Downscattering in Laser-Induced Fusioning Plasmas
Finis H. Southworth, Hugh D. Campbell
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 434-436
Technical Note | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31656