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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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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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A Gas Sorption-Desorption Method for Recovering Plutonium Hexafluoride
Sidney Katz, George I. Cathers
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 5-10
Technical Paper and Note | doi.org/10.13182/NT68-A27978
Fluidized-Bed Fluoride Volatility Processing of Irradiated UO2 Fuels
A. A. Chilenskas
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 11-19
Technical Paper and Note | doi.org/10.13182/NT68-A27979
Suppression of Radioiodine Releases from a Radiochemical Separations Plant
S. R. Smith
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 20-23
Technical Paper and Note | doi.org/10.13182/NT68-A27980
Advantages and Applications of 252Cf as a Neutron Source
W. C. Reinig
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 24-25
Technical Paper and Note | doi.org/10.13182/NT68-A27981
Hafnium Control Rod Behavior in the Shippingport Pressurized Water Reactor
G. J. Salvaggio
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 26-34
Technical Paper and Note | doi.org/10.13182/NT68-A27982
Stability of Nuclear Rocket Engine Dynamics
Donald M. Wiberg, Jan S. Woyski
Nuclear Technology | Volume 5 | Number 1 | July 1968 | Pages 35-45
Technical Paper and Note | doi.org/10.13182/NT68-A27983
A Passive Safety Device Against a Melt-Through Accident
S. M. Zivi
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 53-54
Technical Paper and Note | doi.org/10.13182/NT68-A27949
A 124Sb-Be Source of Thermal Neutrons for Precision Analysis and Tracer Production
W. E. Downs
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 55-61
Technical Paper and Note | doi.org/10.13182/NT68-A27950
Estimates of Ozone Yields in Proposed Chemonuclear Reactors
John T. Sears, James W. Sutherland
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 62-63
Technical Paper and Note | doi.org/10.13182/NT68-A27951
Recovery of Radioactive Cesium on Titanium Phosphate
C. Beaudet, J. Cremer
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 64-67
Technical Paper and Note | doi.org/10.13182/NT68-A27952
Injection Casting Aluminum-10 Wt% Plutonium Fuel Elements
G. E. Miller
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 68-73
Technical Paper and Note | doi.org/10.13182/NT68-A27953
Population Exposure Probability Model for Random Reentry of a Radioisotope Source
C. R. Easton, R. W. Langley, G. H. Anno
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 74-78
Technical Paper and Note | doi.org/10.13182/NT68-A27954
Gamma-Ray Shielding Studies with Monoenergetic Gamma Rays from Positron Annihilation
J. A. Lonergan, D. F. Herring
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 79-84
Technical Paper and Note | doi.org/10.13182/NT68-A27955
Energy-Loss Neutron Experiments with a Reactor
William L. Whittemore
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 85-90
Technical Paper and Note | doi.org/10.13182/NT68-A27956
Improved Resolution in Alpha Autoradiographs
A. T. Jeffs
Nuclear Technology | Volume 5 | Number 2 | August 1968 | Pages 91-93
Technical Paper and Note | doi.org/10.13182/NT68-A27957
A Filter for Fast Flux Testing in a Thermal Test Reactor
R. E. Wood, J. F. Kunze, F. L. Sims, C. S. Robertson, Jr.
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 105-113
Technical Paper and Note | doi.org/10.13182/NT68-A28039
A Sol-Gel Process for Preparing Dense Forms of PuO2
M. H. Lloyd, R. G. Haire
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 114-122
Technical Paper and Note | doi.org/10.13182/NT68-A28040
Fuel Assembly Performance in Piqua Core I
K. J. Miller, W. R. McCurnin
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 123-129
Technical Paper and Note | doi.org/10.13182/NT68-A28041
Dependence of Heat Flux Distribution on Fissile Material Distribution in Fuel
P. Grillo, G. Testa
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 130-139
Technical Paper and Note | doi.org/10.13182/NT68-A28042
Chemical Enrichment of Mercury Isotopes by Neutron Irradiation of Diphenylmercury in Solution
K. E. Collins, C. H. Collins
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 140-144
Technical Paper and Note | doi.org/10.13182/NT68-A28043
High Voltage Gamma-Electric Cell Operation
H. T. Sampson, G. H. Miley
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 145-155
Technical Paper and Note | doi.org/10.13182/NT68-A28044
Compatibility of Materials with Alkali Metals for Space Nuclear Power Systems
W. O. Harms, A. P. Litman
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 156-172
Technical Paper and Note | doi.org/10.13182/NT68-A28045
An In-Core Radiation Detector for Monitoring Pulsed Reactor Excursions
W. H. Todt
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 173-178
Technical Paper and Note | doi.org/10.13182/NT68-A28046
Systems for Experimental Isotope Irradiation in a Production Reactor
G. B. Cole, G. F. Haase, W. R. Kennedy
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 179-182
Technical Paper and Note | doi.org/10.13182/NT68-A28047
Gamma-Ray Assay of Plutonium-238 in Waste Drums
W. W. Strohm
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 183-189
Technical Paper and Note | doi.org/10.13182/NT68-A28048
A Boundary-Layer Diffusion Model of Fission-Product Release from Reactor Fuels
C. E. Miller, Jr.
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 198-205
Technical Paper and Note | doi.org/10.13182/NT68-A28019
A Gas Sorption-Desorption Method for Separating the Hexafluorides of Neptunium and Uranium
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 206-210
Technical Paper and Note | doi.org/10.13182/NT68-A28020
Fast Spectrum Breeder Reactor Analysis
Carroll B. Mills
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 211-217
Technical Paper and Note | doi.org/10.13182/NT68-A28021
Effect of Metallurgical Composition of Aluminum-Uranium-Silicon Fuels on Chemical Reprocessing
Bernice E. Paige, Kenneth L. Rohde
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 218-223
Technical Paper and Note | doi.org/10.13182/NT68-A28022
Crystallization Characteristics of Acidic Uranyl Nitrate Solutions
R. C. Kispert, J. H. Cavendish, N. R. Leist, G. P. Miller
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 224-227
Technical Paper and Note | doi.org/10.13182/NT68-A28023
Irradiation Effects in 2103/R3 Steel: Comparison Between Different Heats and Different Fabrication Procedures
M. Grounes
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 228-235
Technical Paper and Note | doi.org/10.13182/NT68-A28024
Continuous Carbon Meter for Sodium Systems
John M. McKee, Wayne H. Caplinger, Morris Kolodney
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 236-246
Technical Paper and Note | doi.org/10.13182/NT68-A28025
Fission Rate Measurements in Low-Power Fast Critical Assemblies with Solid-State Track Recorders
James H. Roberts, Song-Teh Huang, Roland J. Armani, Raymond Gold
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 247-252
Technical Paper and Note | doi.org/10.13182/NT68-A28026
Some Practical Applications of Gamma-Ray Spectral Resolution to Radionuclide Determination
M. E. Pruitt, Sue H. Prestwood, H. A. Parker
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 253-259
Technical Paper and Note | doi.org/10.13182/NT68-A28027
Geographic Characterization of Chromium Ore Deposits by Elemental Analysis
Henry H. Kramer, W. J. Hampton, Victor J. Molinski, James J. Finn, Werner H. Wahl
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 260-262
Technical Paper and Note | Technical Note | doi.org/10.13182/NT68-A28028
Transport Phenomena at Liquid-Metal-Vapor Interfaces Using Radioactive Tracers
K. F. Wylie, C. E. Dryden
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 263-268
Technical Paper and Note | doi.org/10.13182/NT68-A28029
Proton Reaction Determination of Lithium and Fluorine in Molten Salt Reactor Graphite
R. L. Macklin, J. H. Gibbons, E. Ricci, T. Handley, D. Cuneo
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 269-274
Technical Paper and Note | doi.org/10.13182/NT68-A28030
Neutron Dosimetry Studies in EBR-II
J. L. Jackson, J. A. Ulseth
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 275-282
Technical Paper and Note | doi.org/10.13182/NT68-A28031
Correlation of Tensile and Fatigue Properties of Irradiated Type-347 Stainless Steel at Room Temperature
M. Kangilaski, F. R. Shober
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 283-285
Technical Paper and Note | Technical Note | doi.org/10.13182/NT68-A28032
Effect of Power Changes on Fission-Product Gas Release from UO2 Fuel
R. Soulhier, M. J. F. Notley
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 296-298
Technical Papers and Note | doi.org/10.13182/NT68-A27993
Removal of the Sodium Bond from Sintered (U, Pu) C Fuel Pellets
Felix B. Litton, John H. Bender
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 299-301
Technical Papers and Note | doi.org/10.13182/NT68-A27994
Power Cost Reduction by Crossed-Progeny Fueling of Thermal and Fast Reactors
L. W. LANG
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 302-310
Technical Papers and Note | doi.org/10.13182/NT68-A27995
Milling Technology of Uranium Ores
Alvin H. Ross, Leonard G. Guglielmin
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 311-318
Technical Papers and Note | doi.org/10.13182/NT68-A27996
Optimization of Reactor Irradiation Schedules for Radioisotopes Production According to Demand
A. Morales-Amado, A. M. Martínez-Leal
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 319-321
Technical Papers and Note | doi.org/10.13182/NT68-A27997
Nuclear Radiation Dose Rate Influence on Thermocouple Calibration
Gary J. Dau, R. R. Bourassa, S. C. Keeton
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 322-328
Technical Papers and Note | doi.org/10.13182/NT68-A27998
Corrosion-Resistant Heated Transfer Tubes for Molten Metals and Salts
D. E. Grosvenor, I. O. Winsch, W. E. Miller, G. J. Bernstein, R. D. Pierce
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 329-332
Technical Papers and Note | doi.org/10.13182/NT68-A27999
A Glovebox System for a Spectrophotometer
D. A. Costanzo, L. T. Corbin
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Page 333
Technical Papers and Note | doi.org/10.13182/NT68-A28000
The Effects of Ground Roughness on Fallout Protection Factors
R. L. French, J. H. Price
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 334-343
Technical Papers and Note | doi.org/10.13182/NT68-A28001
Sodium Analysis by Spark Source Mass Spectrography
Edgar Berkey, George G. Sweeney, William M. Hickam
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 344-353
Technical Papers and Note | doi.org/10.13182/NT68-A28002
Leakage Rate Measurements by Means of Oxygen Determination
J. Kuypers, J. P. Ruiter
Nuclear Technology | Volume 5 | Number 5 | November 1968 | Pages 354-361
Technical Papers and Note | doi.org/10.13182/NT68-A28003
Possibilities and Advantages of Using Negative Pions in Radiotherapy
Louis Rosen
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 379-388
Technical Paper and Note | doi.org/10.13182/NT68-A27964
Notch Ductility Properties of SM-1A Reactor Pressure Vessel Following the In-Place Annealing Operation
Uldis Potapovs, J. Russell Hawthorne, Charles Z. Serpan, Jr.
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 389-409
Technical Paper and Note | doi.org/10.13182/NT68-A27965
A Correction Factor for In-Reactor Sintering of Fast Oxide Fuels
E. G. Stevens
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 410-416
Technical Paper and Note | doi.org/10.13182/NT68-A27966
A Jaw Crusher for Plutonium Ceramics
J. E. Ayer, H. Osuna
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 417-423
Technical Paper and Note | doi.org/10.13182/NT68-A27967
A Nuclear Thermionic Space Power Concept Using Rod Control and Heat Pipes
John L. Anderson, Edward Lantz
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 424-436
Technical Paper and Note | doi.org/10.13182/NT68-A27968
Method for Estimating Critical Velocity for Damage to Reentering Fuels Impacting End On
Calvin C. Silverstein
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 437-444
Technical Paper and Note | doi.org/10.13182/NT68-A27969
Neutron Diffusion Parameters of Perfluorodimethylcyclohexane Using a Two-Region Pulsed-Neutron Technique
C. A. Bisselle, John A. Wethington, Jr.
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 445-455
Technical Paper and Note | doi.org/10.13182/NT68-A27970
Gamma Heating in Thin Heavy-Element Absorbers
John H. Lynch, Richard J. Crum, Harry J. Reilly
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 456-463
Technical Paper and Note | doi.org/10.13182/NT68-A27971
Calculation of Concentration Behavior During Chemical Decontamination of a Nuclear Reactor Plant
S. K. Beal, D. R. Henderson
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 464-467
Technical Paper and Note | doi.org/10.13182/NT68-A27972