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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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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Experimental Emergency Core Cooling Results from LOFT Non-Nuclear Tests
L. P. Leach, L. J. Ybarrondo, G. D. McPherson
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 126-149
Technical Paper | Reactor | doi.org/10.13182/NT77-A31772
The Interaction and Protection of Superconducting Poloidal Field Coils and Toroidal Field Coils in a Tokamak Experimental Power Reactor
H. T. Yeh, J. W. Lue
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 150-160
Technical Paper | Reactor | doi.org/10.13182/NT77-A31773
Bypass Flow Distribution in a Boiling Water Reactor
Roger W. Carlson, David R. Gott
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 161-173
Technical Paper | Reactor | doi.org/10.13182/NT77-A31774
Energy Investment in Nuclear and Solar Power Plants
G. Moraw, M. Schneeberger, A. Szeless
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 174-183
Technical Paper | Reactor | doi.org/10.13182/NT77-A31775
Plutonium Assemblies in Reload 1 of the Dodewaard Reactor
H. Bairiot, P. Deramaix, C. Vandenberg, L. Leenders, P. Mostert
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 184-202
Technical Paper | Reactor | doi.org/10.13182/NT77-A31776
The Human Cost of Regulatory Delays
Tobias W. T. Burnett
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 203-211
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31777
Analysis of Electrical Power Generation Costs
R. W. Hardie, J. H. Chamberlin
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 212-222
Technical Paper | Economic | doi.org/10.13182/NT77-A31778
An Anomalous Reactivity Meter
H. A. Larson, J. I. Sackett
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 223-230
Technical Paper | Instrument | doi.org/10.13182/NT77-A31779
Thermographic Imaging of Nuclear Fuel Rods
Sidney Oldberg, Jr., Richard C. Honey, David G. Falconer, Edwin L. Zebroski
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 231-234
Technical Paper | Instrument | doi.org/10.13182/NT77-A31780
Minimum Critical Mass of Plutonium-Polyethylene System Found to Be Significantly Lower Than Plutonium-Water System
Jack K. Thompson
Nuclear Technology | Volume 33 | Number 2 | April 1977 | Pages 235-236
Technical Note | Chemical Processing | doi.org/10.13182/NT77-A31781
Combined Free and Forced Convection Effects on Transient Temperature Distributions in a Scaled-Down Model of the Inlet Plenum of the SNR-300 Reactor
J. F. L. M. Brukx, G. P. R. Hansen, P. Voj
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 5-16
Technical Paper | Reactor | doi.org/10.13182/NT77-A31759
Experimental Verification of a Method for Simulating a Boiling Water Reactor Core Based on a Few-Group Coarse-Mesh Diffusion Scheme
Sadao Uchikawa
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 17-29
Technical Paper | Reactor | doi.org/10.13182/NT77-A31760
Plutonium Release from Burning Sodium
J. L. Stakebake, H. N. Robinson
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 30-39
Technical Paper | Reactor | doi.org/10.13182/NT77-A31761
Experimental Investigation of Fuel-Coolant Interaction
Wiktor Śyszkowski
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 40-59
Technical Paper | Fuel | doi.org/10.13182/NT77-A31762
Analysis of the Venting System of the Gas-Cooled Fast Breeder Reactor Fuel Element for Various Operating Conditions
Klaus W. Klein
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 60-67
Technical Paper | Fuel | doi.org/10.13182/NT77-A31763
Preparation and Characterization of Sintered Glass-Ceramics from Calcined Simulated High-Level Waste
E. G. Samsel, J. R. Berreth
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 68-75
Technical Paper | Radioactive Waste | doi.org/10.13182/NT77-A31764
Mechanical Properties of Liquid-Metal Fast Breeder Reactor Primary Piping Materials
Charles R. Brinkman, Vinod K. Sikka, Roy T. King
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 76-95
Technical Paper | Material | doi.org/10.13182/NT77-A31765
Modification of the Existing Yielding Creep Theory of Irradiation Creep in Zirconium and Zircaloy-2
P. K. Madden, R. V. Hesketh
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 96-102
Technical Paper | Material | doi.org/10.13182/NT77-A31766
Neutron Flux Measurement at the LAMPF Radiation Effects Facility
Dennis G. Perry, Margaret L. Simmons, James S. Gilmore
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 103-109
Technical Paper | Accelerator | doi.org/10.13182/NT77-A31767
Comment on the Interpretation and Application of Limiting Critical Concentrations of Fissile Nuclides in Water
E. D. Clayton, B. M. Durst
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 110-111
Technical Note | Chemical Processing | doi.org/10.13182/NT77-A31768
The Effect of Chemistry Variations on the Short-Term Rupture Life and Tensile Properties of 20% Cold-Worked Type 316 Stainless Steel
D. R. Duncan, M. M. Paxton
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 112-119
Technical Note | Material | doi.org/10.13182/NT77-A31769
Reactor Containment Heat Removal by Passive Heat Sinks Following a Loss-of-Coolant Accident
P. S. Ayyaswamy, J. N. Chung, K. K. Niyogi
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 243-247
Technical Paper | Reactor | doi.org/10.13182/NT77-A31785
A Study of Post-Accident Molten Fuel Downward Streaming Through the Axial Shield Structure in the Liquid-Metal Fast Breeder Reactor
Ronald D. Gasser, Mujid S. Kazimi
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 248-259
Technical Paper | Reactor | doi.org/10.13182/NT77-A31786
Removal of Iodine from Reactor Fuel Solutions as Insoluble Pdl2
J. C. Mailen, D. E. Horner
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 260-263
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31787
Nuclear Heating in a Control Element of a Gas-Cooled Fast Breeder Reactor
A. Razani, S. Yee, M. Nagel
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 264-274
Technical Paper | Fuel | doi.org/10.13182/NT77-A31788
Nonequilibrium Evaporation and Condensation in Liquid-Metal Fast Breeder Reactor Fuel Expansion
J. G. Refling, A. B. Reynolds, P. L. Garner, S. P. Rao
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 275-289
Technical Paper | Fuel | doi.org/10.13182/NT77-A31789
The Determination of Defective Particle Fraction in High-Temperature Gas-Cooled Reactor Fuels
D. E. LaValle, D. A. Costanzo, W. J. Lackey, A. J. Caputo
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 290-295
Technical Paper | Fuel | doi.org/10.13182/NT77-A31790
New Methods for Measuring Neutron Spectra with Energy from 0.4 eV to 10 MeV by Track and Activation Detectors
J. J. Doroshenko, S. N. Kraitor, T. V. Kuznetsova, K. K. Kushnereva, E. S. Leonov
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 296-304
Technical Paper | Instrument | doi.org/10.13182/NT77-A31791
Dual Gauging Utilizing Penetrating and Scattered Photon Fluxes
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 305-313
Technical Paper | Instrument | doi.org/10.13182/NT77-A31792
Pressure Drop of Spacer Grids in Smooth and Roughened Rod Bundles
K. Rehme
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 314-317
Technical Note | Fuel | doi.org/10.13182/NT77-A31793
The Spatial Variation of the Damage Energy and Gas Production in the Experimental Volume of a Li(D,n) Neutron Radiation Damage Facility
R. G. Alsmiller, Jr., J. Barish
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 318-321
Technical Note | Material | doi.org/10.13182/NT77-A31794
