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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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 Flow Experiment on a Curved-Porous-Wall Gas-Core Reactor Geometry
Chester D. Lanzo
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 6-12
Reactor | doi.org/10.13182/NT70-A28628
Pilot Plant Studies of Methyl Iodide Cleanup by Sprays
L. F. Parsly
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 13-22
Chemical Processing | doi.org/10.13182/NT70-A28629
Porous UO2 Bodies Produced by Reduction of U3O8
T. N. Washburn
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 23-28
Fuel | doi.org/10.13182/NT70-A28630
Refluxing Capsule Experiments with Refractory Metals and Boiling Alkali Metals
J. R. DiStefano, J. H. Devan
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 29-44
Fuel | doi.org/10.13182/NT70-A28631
Economics of Desalting Water and Generating Electricity in Singapore
William R. Bohl, Jerry L. Gillette, Max W. Carbon
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 45-51
Economic | doi.org/10.13182/NT70-A28632
The Interaction of Tellurium Dioxide and Water Vapor
A. P. Malinauskas, J. W. Gooch, Jr., J. D. Redman
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 52-57
Material | doi.org/10.13182/NT70-A28633
The Dissolution of Metal Corrosion Products in Deionized Water at 38° C (100° F)
Barbara A. Johnson
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 58-61
Material | doi.org/10.13182/NT70-A28634
Cesium Purification by Zeolite Ion Exchange
B. W. Mercer, L. L. Ames, P. W. Smith
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 62-69
Radioisotope | doi.org/10.13182/NT70-A28635
Alpha Monitor for Rapid Contamination Screening of Hands and Shoes
W. F. Splichal, Jr.
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 70-72
Radiation | doi.org/10.13182/NT70-A28636
Applications of Rare Earth Tracers to Gunpowder Residues
K. K. S. Pillay, C. C. Thomas, Jr., D. M. Hart, D. Didising, R. C. Thomas
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 73-78
Analysis | doi.org/10.13182/NT70-A28637
Nondestructive Assay of Fissionable Materials
D. W. Jones, P. R. Malmberg, T. H. May, C. V. Strain
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 79-83
Analysis | doi.org/10.13182/NT70-A28638
Pulse Rate Correlation in Dynamic Experiments
Rocco A. Fazzolare
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 84-87
Technique | doi.org/10.13182/NT70-A28639
On the Gamma-Ray One-Shot-Collimator Measurement of Two-Phase-Flow Void Fractions
R. P. Gardner, R. H. Bean, J. K. Ferrell
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 88-94
Technique | doi.org/10.13182/NT70-A28640
A Convenient Technique for Techniques Stirring Liquid Sodium
M. R. Hobdell, F. J. Salzano
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 95-96
Technique | doi.org/10.13182/NT70-A28641
Molten-Salt Reactors—History, Status, and Potential
M. W. Rosenthal, P. R. Kasten, R. B. Briggs
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 107-117
Reactor | doi.org/10.13182/NT70-A28619
Experience with the Molten-Salt Reactor Experiment
Paul N. Haubenreich, J. R. Engel
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 118-136
Reactor | doi.org/10.13182/NT8-2-118
Molten-Salt Reactor Chemistry
W. R. Grimes
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 137-155
Reactor | doi.org/10.13182/NT70-A28621
New Developments in Materials for Molten-Salt Reactors
H. E. McCoy, R. L. Beatty, W. H. Cook, R. E. Gehlbach C. R. Kennedy, J. W. Koger, A. P. Litman, C. E. Sessions, J. R. Weir
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 156-169
Reactor | doi.org/10.13182/NT70-A28622
Engineering Development of the MSBR Fuel Recycle
M. E. Whatley, L. E. McNeese, W. L. Carter, L. M. Ferris, E. L. Nicholson
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 170-178
Reactor | doi.org/10.13182/NT70-A28623
Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor Design
Dunlap Scott, W. P. Eatherly
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 179-189
Reactor | doi.org/10.13182/NT70-A28624
The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor
E. S. Bettis, Roy C. Robertson
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 190-207
Reactor | doi.org/10.13182/NT70-A28625
Reactor Physics and Fuel-Cycle Analyses
A. M. Perry, H. F. Bauman
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 208-219
Reactor | doi.org/10.13182/NT70-A28626
Measurement of Control Schemes for Fast-Spectrum Compact Reactors
J. F. Kunze, F. L. Sims, J. M. Byrne, R. E. Reid
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 226-239
Paper | Reactor | doi.org/10.13182/NT70-A28669
N-Reactor-WPPSS Complex Operating Performance
Emil E. Leitz
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 240-245
Paper | Reactor | doi.org/10.13182/NT70-A28670
The Measurement of Radial Power Distributions in a Triga Fuel Element during Reactor Power Excursions
W. A. Goodwin, M. E. Wyman
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 246-254
Paper | Reactor | doi.org/10.13182/NT70-A28671
An Experimental Analysis Of Fission-Gas Holdup Beds
Dwight W. Underhill
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 255-260
Paper | Fuel | doi.org/10.13182/NT70-A28672
Stationary Gas Bubbles in Narrow Liquid-Filled Gaps
H. O. Schad, A. A. Bishop
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 261-275
Paper | Fuel | doi.org/10.13182/NT70-A28673
Well-Logging Research for Geonuclear Technology
J. R. Hearst, R. C. Carlson
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 276-282
Paper | Nuclear Explosive | doi.org/10.13182/NT70-A28674
Void-Space Analysis by Use of Thermal-Neutron Analysis Irradiated Air (41Ar)
Jerry B. F. Champlin
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 283-289
Paper | Analysis | doi.org/10.13182/NT70-A28675
Application of Neutron Activation Analysis to the Sweat Test Diagnosis of Cystic Fibrosis
Robert G. McAndrew, James B. Smathers, , Richard E. Wainerdi, G. M. Harrison, Robert Doggett
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 290-295
Paper | Analysis | doi.org/10.13182/NT70-A28676
Experimental Determination of the Differential Fast-Neutron Flux in the High Flux Isotope Reactor Using Techniques Threshold Detectors
H. L. Dodds, Jr., P. F. Pasqua
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 296-301
Paper | Technique | doi.org/10.13182/NT70-A28677
Reactor Neutron Measurements with Fission Foil-Lexan Detectors
P. F. Rago, N. Goldstein, E. Tochilin
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 302-309
Paper | Technique | doi.org/10.13182/NT70-A28678
The Iodine Collection Efficiency of Activated Charcoal from Hanford Reactor Confinement Systems
J.D. Ludwick
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 310-313
Note | Chemical Processing | doi.org/10.13182/NT70-A28679
Replacement Hafnium Control Rods for the Bonus Reactor
G. M. Tolson, G. R. Davis
Nuclear Technology | Volume 8 | Number 3 | March 1970 | Pages 314-320
Note | Material | doi.org/10.13182/NT70-A28680
Accuracy of Power-Distribution Calculation Methods for Uranium and Plutonium Lattices
A. Ariemma, G. Lesnoni La Parola, M. Paoletti Gualandi, P. Peroni, B. Zaffiro
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 328-354
Reactor | doi.org/10.13182/NT70-A28661
A Gaseous-Core Reactor Concept for Electrical Power Generation
Eugene C. Gritton, Benjamin Pinkel
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 355-370
Reactor | doi.org/10.13182/NT70-A28662
Processing of Highly Irradiated Al-Pu Alloy
R. Berger, G. Koehly, C. Musikas, R. Pottier, R. Sontag
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 371-379
Chemical Processing | doi.org/10.13182/NT70-A28663
A Dislocation Etch for Uranium Dioxide
Michael F. Ehman, J. W. Faust, Jr.
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 380-383
Fuel | doi.org/10.13182/NT70-A28664
Capacity Expansion Optimization in a Growing Nuclear Fuel Fabrication Industry
F. J. Homan, T. N. Washburn
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 384-394
Economic | doi.org/10.13182/NT70-A28665
Time-Optimal Digital Control of Zero-Power Nuclear Reactors
Thomas J. Marciniak
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 401-416
Paper | Reactor | doi.org/10.13182/NT70-A28685
Irradiation Performance of Pyrolytic-Carbon- and Silicon-Carbide-Coated Fuel Particles
P. E. Reagan, E. L. Long, Jr., J. G. Morgan, J. H. Coobs
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 417-431
Paper | Fuel | doi.org/10.13182/NT70-A28686
Design and Tests of Null-balanced Fission Gas Pressure Transducer and Controller
John R. Folkrod
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 432-436
Paper | Fuel | doi.org/10.13182/NT70-A28687
The Economics of Blending and Diffusion in Uranium Recycle
A. MacCragh
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 437-444
Paper | Economic | doi.org/10.13182/NT70-A28688
Engineering Design of an Instrumented Pilot Plant for Remote Reactions-Radiation-Induced Polymerization
F. T. Osborne, S. Omi, V. T. Stannett, E. P. Stahel
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 445-449
Paper | Radioisotopes | doi.org/10.13182/NT70-A28689
Dose Rates in a Slab Phantom from Monoenergetic Gamma Rays
H. C. Claiborne, D. K. Trubey
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 450-455
Paper | Shielding | doi.org/10.13182/NT70-A28690
Factors Involved in On-Stream Trace Activation Analysis
H. Al-Shahristani, R. E. Jervis
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 456-464
Paper | Analysis | doi.org/10.13182/NT70-A28691
Radioisotope Neutron Activation Analyzer for Process Control Analysis
Juhani Kuusi
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 465-473
Paper | Analysis | doi.org/10.13182/NT70-A28692
Increasing Maximum Enrichment Processing Capability Through Criticality Calculations
D. L. Dunaway, G. P. Miller, W. A. Johnson
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 482-487
Fuel Cycle | doi.org/10.13182/NT70-A28647
Gas Pulse Impregnation of Graphite with Carbon
R. L. Beatty, D. V. Kiplinger
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 488-495
Fuel | doi.org/10.13182/NT70-A28648
Plutonium Recycling in Heavy-Water-Moderated Thorium Reactor Systems
J. Darvas, U. Hansen, E. Teuchert
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 496-506
Fuel | doi.org/10.13182/NT70-A28649
Compatibility of (U,Th)O2 with Graphite During Irradiation
J. A. Conlin, D. R. Cuneo, E. L. Long, Jr., C. L. Segasser
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 507-515
Material | doi.org/10.13182/NT70-A28650
The Rapid Acquisition and Analysis of Gamma-Spectrometer Data Using a Small Computer
N. I.Sax, J. C. Daly
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 516-521
Instrument | doi.org/10.13182/NT70-A28651
Use of a Pulse Detector for Reactor Noise Measurements
J. R. Trinko, Jr., S. H. Hanauer
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 522-530
Technique | doi.org/10.13182/NT70-A28652
Neutron Source-Strength Determination by Student Laboratories
B. W. McGhee, W. W. Graham, III, M. R. Haroon
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 531-535
Education | doi.org/10.13182/NT70-A28653
Fabrication of a 238Pu Heat Source for a Cardiac Pacemaker
D. L. Fleming, C. O. Brewer, D. L. Coffey
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 536-538
Radioisotope | doi.org/10.13182/NT70-A28654
