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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Modeling of Thermionic Reactor Systems for Dynamics Studies
J. G. Guppy, R. L. Brehm
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 7-18
Technical Paper | Reactor | doi.org/10.13182/NT71-A30897
Pulsed-Neutron and Exponential Experiments with Mixed-Fuel Lattices
Pekka Jauho, Risto Tarjanne
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 19-28
Technical Paper | Reactor | doi.org/10.13182/NT71-A30898
A Vibrating Bar Technique for Preparing Carbon Microspheres
C. R. Schmitt
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 29-37
Technical Paper | Chemical Processing | doi.org/10.13182/NT71-A30899
Application of Fuel-Element Modeling Codes to EBR-II Driver Fuel
C. M. Walter, P. G. Shewmon, J. P. Bacca
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 38-44
Technical Paper | Fuel | doi.org/10.13182/NT71-A30900
Influence of Irradiation Temperature on the Creep-Rupture Properties of Hastelloy-N
H. E. McCoy, R. E. Gehlbach
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 45-60
Technical Paper | Material | doi.org/10.13182/NT71-A30901
Techniques in Monte Carlo Analysis Applied to the Nuclear Density Gauge
P. C. Curtayne
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 61-74
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30902
Californium-252 Neutron Sources for Industrial Applications
A. R. Boulogne, J. P. Faraci
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 75-83
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30903
A Useful Recurrence Formula for the Equations of Radioactive Decay
John N. Hamawi
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 84-88
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30904
Calorimetric Determination of Relative Gamma Heating in Materials of Various Thicknesses and Atomic Numbers
Harry J. Reilly, Lawrence E. Peters, Jr.
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 89-95
Technical Paper | Shielding | doi.org/10.13182/NT71-A30905
Reciprocal Multiplication Meter
W. R. Sheets
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 96-98
Technical Paper | Instrument | doi.org/10.13182/NT71-A30906
Alpha-Particle Densitometer with Variable Response
Werner Brandt, Michael D. D’Agostino, Anthony J. Favale
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 99-104
Technical Paper | Instrument | doi.org/10.13182/NT71-A30907
Exposure Angular Distributions in Air Above Disk Isotropic Cobalt-60 Sources
R. M. Rubin, R. E. Faw
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 105-114
Technical Paper | Radiation | doi.org/10.13182/NT71-A30908
An Equilibration Method for Measuring Low-Oxygen Activities in Liquid Sodium
D. L. Smith
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 115-119
Technical Paper | Analysis | doi.org/10.13182/NT71-A30909
Measurement of Neutron Fluence by Neptunium-237 and Uranium-238 Fission Dosimeters
K. M. Barry, J. A. Corbett
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 120-130
Technical Paper | Analysis | doi.org/10.13182/NT71-A30910
Determination of Pyrocarbon Thermal Conductivity by the Burst-Reactor Technique
Peter G. Salgado, Fred P. Schilling, Gerald T. Brock, Kermit L. Holman
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 131-143
Technical Paper | Technique | doi.org/10.13182/NT71-A30911
An Expository Derivation of Neutron Transport Equations
A. A. Harms, S. I. Schreiner
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 144-149
Technical Paper | Education | doi.org/10.13182/NT71-A30912
An Analytical Reactor Excursion Model with Delayed Neutrons
B. E. Leonard
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 159-174
Technical Paper | Reactor | doi.org/10.13182/NT71-A30881
Comparison of Experimentally Measured and Calculated Radiation Environment Internal to the PAX R-1 Reactor
D. J. Hill, W. D. Rankin
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 175-184
Technical Paper | Reactor | doi.org/10.13182/NT71-A30882
Critical Experiments with Unmoderated Plutonium Oxide
S. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 185-190
Technical Paper | Reactor | doi.org/10.13182/NT71-A30883
A Capillary Valve for Use in the Ventilation of Fast Breeder Control Rods
William A. Heenan, David T. Camp
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 191-205
Technical Paper | Fuel | doi.org/10.13182/NT71-A30884
Apparatus for Study of In-Pile Creep of Fuels
R. A. Robinson, S. J. Basham, J. S. Perrin
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 206-212
Technical Paper | Fuel | doi.org/10.13182/NT71-A30885
Nondestructive Testing of Encapsulated Radioactive Cesium and Strontium
R. W. Steffens, J. C. Crowe, G. L. Borsheim, J. C. Wormeli
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 213-221
Technical Paper | Radioactive Waste | doi.org/10.13182/NT71-A30886
Selection of Steam Generator Tubing Material for the Westinghouse LMFBR Demonstration Plant
W. E. Ray, S. L. Schrock, S. A. Shiels, K. C. Thomas
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 222-231
Technical Paper | Material | doi.org/10.13182/NT71-A30887
Reentry Protection for Radioisotope Heat Sources
S. E. Bramer, H. Lurie, T. H. Smith
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 232-245
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30888
A Calculation of Neutron-Induced Physical Doses in Human Tissues
J. J. Ritts, M. Solomito, P. N. Stevens
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 246-258
Technical Paper | Radiation | doi.org/10.13182/NT71-A30889
An In-Core Furnace for the High-Temperature Irradiation Testing of Reactor Fuels
E. E. Anderson, S. Langer, N. L. Baldwin, F. E. Vanslager
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 259-265
Technical Paper | Technique | doi.org/10.13182/NT71-A30890
An Inexpensive Pump for Liquid Sodium
R. R. Schlueter, W. E. Ruther
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 266-267
Technical Note | Reactor | doi.org/10.13182/NT71-A30891
A Note on the Use of the Tchebycheff Criterion for Determination of Parameters in Empirical Approximations to Gamma-Ray Buildup Factor Data
A. F. Vetter, A. B. Chilton
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 268-269
Technical Note | Shielding | doi.org/10.13182/NT71-A30892
The Soviet Program on Nuclear Explosives for the National Economy
Glenn C. Werth
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 280-302
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30862
The Use of Multiple Nuclear Explosives for Gas Stimulation
Milo D. Nordyke
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 303-314
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30863
Plowshare and the Environment
Alfred Holzer
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 315-322
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30864
A Method for Estimating the Risk from a Plowshare Detonation
Harry J. Otway, Ronald K. Lohrding, Morris E. Battat
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 323-330
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30865
The Need for Plowshare Gas
Sam Smith
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 331-334
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30866
Radiological Considerations in the Use of Natural Gas from Nuclearly Stimulated Wells
C. J. Barton, D. G. Jacobs, M. J. Kelly, E. G. Struxness
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 335-344
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30867
Recovery of High-Viscosity Petroleum by Steam from Geothermal Heat
Fernando Paz-Castillo, Paul Kruger
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 345-356
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30868
Neutron Shielding of Underground Nuclear Explosives
Joseph B. Green, Jr., Richard M. Lessler
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 357-366
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30869
Leaching of Chalcopyrite (CuFeS2) with Sodium Chloride Sulfuric Acid Solutions
Fausto J. Muñoz-Ribadeneira, Henry J. Gomberg
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 367-371
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30870
The Marvel Experiment
B. K. Crowley, H. D. Glenn
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 372-378
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30871
Microfracturing in Postshot Gasbuggy Core GB-3
I. Y. Borg
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 379-389
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30872
The Chemistry of the Gasbuggy Chimney
Russell E. Duff, Lew Schalit
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 390-399
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30873
On-Line Monitor of Natural Gas Lines for Hydrogen-3 and Krypton-85
Robert S. Brundage, Bill G. Motes, Preston Gant
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 400-405
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30874
Fate of Schooner Fallout Radionuclides Ingested by the Dairy Cow
G. D. Potter, G. M. Vattuone, D. R. McIntyre
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 406-412
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30875
Radionuclide Distribution in the Particle Population Produced by the Schooner Cratering Detonation
Robert E. Heft, William Phillips, William Steele
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 413-443
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30876
Biological Implications of Nuclear Debris in Aquatic Ecosystems
Florence L. Harrison
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 444-458
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30877
Distribution, Residence Time, and Inventory of Tritium in Sedan Crater Ejecta
J. R. Martin, J. J. Koranda
Nuclear Technology | Volume 11 | Number 3 | July 1971 | Pages 459-465
Technical Paper | Nuclear Explosion Engineering / Nuclear Explosive | doi.org/10.13182/NT71-A30878
Effects of Heating Rate and Pressure on Expansion of Zircaloy Tubing During Sudden Heating Conditions
A. D. Emery, D. B. Scott, J. R. Stewart
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 474-478
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30844
Comparison of Rupture Data from Irradiated Fuel Rods and Unirradiated Cladding
D. O. Hobson, M. F. Osborne, G. W. Parker
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 479-490
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30845
Measurement of Light-Water Reactor Coolant Channel Reduction Arising from Cladding Deformation During a Loss-of-Coolant Accident
R. D. Waddell, Jr.
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 491-501
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30846
Fuel Rod Failure Under Loss-of-Coolant Conditions in Treat
R. A. Lorenz, D. O. Hobson, G. W. Parker
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 502-520
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30847
Application of Experimental Data to Analytical Evaluation of Cladding Failure Distribution
B. E. Bingham, A. L. Lowe, Jr.
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 521-525
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30848
The Effects of Clad Swelling on Emergency Core Cooling Performance
Wayne A. Carbiener
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 526-531
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30849
The Effect of Zircaloy-Clad Fuel Rod Failure on BWR Core Spray Cooling
Richard G. Bock, John D. Duncan, James E. Leonard
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 532-543
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30850
The Effect of Fuel Rod Failure on Emergency Core Cooling System Design for Boiling Water Reactors
J. E. Hench, D. J. Liffengren
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 544-550
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30851
Experimental Studies of The Effect of Flow Restrictions in a Small Rod Bundle Under Emergency Core Coolant Injection Conditions
P. R. Davis
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 551-556
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30852
Effect of Flow Blockage on Bottom Flooding Heat Transfer Effectiveness (Flecht)
J. O. Cermak, R. H. Leyse, D. P. Dominicis
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 557-562
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30853
Dynamic Neutronic and Mechanical Measurements with a Pulse Reactor of Uranium-Molybdenum Alloy
John T. Mihalczo, Jon A. Reuscher
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 563-577
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Reactor | doi.org/10.13182/NT71-A30854
Behavior of Mixed Oxide (U,Pu)O2 Fuels as a Function of Temperature and Burnup
R. M. Carroll, O. Sisman
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 578-591
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30855
Through-Thickness Neutron Fluence and Embrittlement Gradients in Reactor Pressure Vessels
C. Z. Serpan, Jr., H. E. Watson
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 592-601
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Material | doi.org/10.13182/NT71-A30856
Underwater Charging Machine for Nuclear Irradiation Sample Insertion
R. M. Collins
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 602-608
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Hot Laboratory | doi.org/10.13182/NT71-A30857
New Encapsulation Techniques for the Fabrication of Californium-252 Neutron Sources
R. D. Baybarz, J. B. Knauer, J. R. Peterson
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 609-615
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Technique | doi.org/10.13182/NT71-A30858