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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Coprocessing Solvent Extraction Studies
Martha S. Okamoto, Major C. Thompson
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 126-131
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16303
Photochemically Produced U(IV) as a Reductant for Pu(IV) and Applications in Nuclear Fuel Reprocessing
G. L. DePoorter, C. K. Rofer-DePoorter, S. W. Hayter
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 132-135
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16304
Removal of Actinides from Selected Nuclear Fuel Reprocessing Wastes
James D. Navratil, Gary H. Thompson
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 136-145
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16305
Design and Operational Characteristics of High-Density Fuel Storage Facilities
E. A. Grimm
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 146-154
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16306
Subsurface Storage of Commercial Spent Nuclear Fuel
L. M. Richards, M. J. Szulinski+
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 155-164
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16307
Spent Fuel Storage Experience
A. B. Johnson, Jr.
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 165-173
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16308
Experience with the Use of Recycle Plutonium in Mixed-Oxide Fuel in Light Water Reactors in the Federal Republic of Germany
H. J. Schenk, K. L. Huppert, W. Stoll
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 174-185
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16309
A Process Control and Safeguards System Plutonium Inventory Control for MOX Fuel Facility
Tsuyoshi Mishima, Minoru Aoki, Tadashi Muto, Tsuyoshi Amanuma
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 186-193
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16310
The Exxon Nuclear Fuel Recovery and Recycling Center: Process Description
G. L. Ritter
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 194-202
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16311
Exxon Nuclear Fuel Recovery and Recycling Center Facility Description
J. E. Birchler, H. L. Caudill
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 203-212
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16312
A Safety Analysis for the Nuclear Fuel Recovery and Recycling Center
L. T. Lakey
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 213-221
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16313
Dynamic Materials Accounting in the Back End of the Light Water Reactor Fuel Cycle
H. A. Dayem, D. D. Cobb, R. J. Dietz, E. A. Hakkila, J. P. Shipley, D. B. Smith
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 222-243
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16314
Liquid Waste Handling Facilities for a Conceptual Light Water Reactor Spent Fuel Reprocessing Complex
D. C. Witt, R. F. Bradley
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 244-258
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16315
Wiped-Film Evaporators for Evaporating Alkaline Light Water Reactor Radioactive Wastes
C. B. Goodlett
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 259-267
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16316
Leach Rates of High Activity Waste from Borosilicate Glass
John R. Wiley
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 268-272
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16317
Some Aspects of the Thermal Analysis of Metal-Encapsulated Spent Fuel
L. J. Jardine, M. J. Steindler
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 273-284
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16318
Engineering Problems of Laser-Driven Fusion Reactors
S. I. Abdel-Khalik, R. W. Conn, G. A. Moses
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 5-21
Technical Paper | Reactor | doi.org/10.13182/NT79-A16170
A Generalized Theory for Predicting Mass Effluence During Reactor Reflooding
K. H. Sun, R. B. Duffey
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 21-27
Technical Paper | Reactor | doi.org/10.13182/NT79-A16171
The Influence of Physics Parameters on Tokamak Reactor Design
David A. Ehst, Kenneth Evans, Jr., Weston M. Stacey, Jr.
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 28-41
Technical Paper | Reactor | doi.org/10.13182/NT79-A16172
Use of Neutron Noise to Detect BWR-4 In-Core Instrument Tube Vibrations and Impacting
D. N. Fry, R. C. Kryter, M. V. Mathis, J. E. Mott, J. C. Robinson
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 42-54
Techinical paper | Reactor | doi.org/10.13182/NT79-A16173
Characteristics of Plutonium-Topped Thorium Cycles in Heavy-Water-Moderated Pressure Tube Reactors
S. Banerjee, F. W. Barclay
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 55-62
Techinical paper | Fuel Cycle | doi.org/10.13182/NT79-A16174
Savannah River Plant Thorium Processing Experience
D. A. Orth
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 63-74
Techinical paper | Chemical processing | doi.org/10.13182/NT79-A16175
Development of the Krypton Absorption in Liquid CO2 (KALC) Process: Mass Transfer Efficiencies of Packed Columns
Thomas Michael Gilliam
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 75-87
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A16176
On the Burnup-Dependent Heat Transfer from Fuel to Cladding in Fast Reactor Fuel Rods
Helmut Elbel, José LóPez Jiménez
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 88-99
Technical Paper | Fuel | doi.org/10.13182/NT79-A16177
Mechanical Behavior of Honeycomb Spot-Welded Spacer Grids Irradiated in Two Fuel Rod Bundles
D. Haas, J. van de Velde, H. Braun
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 100-108
Technical Paper | Material | doi.org/10.13182/NT79-A16178
Electrical Charging of Macroscopic Particles Using a Beta Source and Electric and Magnetic Fields
Robert A. Fjeld, Robert Jennings Heinsohn, Samuel H. Levine
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 109-118
Technical Paper | Radioisotope | doi.org/10.13182/NT79-A16179
Cyclic Purging for Low-Temperature Solid Fusion Reactor Blanket Operation
Gary S. Was, Lawrence M. Lidsky
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 289-300
Technical Paper | Reactor | doi.org/10.13182/NT79-A19218
A Sensitivity Study on the Damage Potential of a Liquid-Metal Fast Breeder Reactor Core Disassembly
R. W. Ostensen
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 301-313
Technical Paper | Reactor | doi.org/10.13182/NT79-A19219
High-Enrichment Steady-State Cascade Performance
George Emanuel
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 314-327
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A19220
The Effects of Grain Boundary Fission Gas on Transient Fuel Behavior
R. J. DiMelfi, L. W. Deitrich
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 328-337
Technical Paper | Fuel | doi.org/10.13182/NT79-A19221
Feasibility Study to Produce First Wall Fusion Reactor Spectra Around a 14-MeV Neutron Point Source
Morris E. Battat, L. A. Ronald Dierckx,+, C. Robert Emigh
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 338-348
Technical Paper | Material | doi.org/10.13182/NT79-A19222
Corrosion Behavior of Selected Structural Materials in a Simulated Steam-Cycle High-Temperature Gas-Cooled Reactor Helium Environment
F. N. Mazandarany, G. Y. Lai
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 349-365
Technical Paper | Material | doi.org/10.13182/NT79-A19223
Radioisotope-Powered Photovoltaic Generator
John W. McKlveen, John Uselman
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 366-372
Technical Paper | Radioisotope | doi.org/10.13182/NT79-A19224
Design Calculations for a 14-MeV Neutron Collimator
R. A. Lillie, R. G. Alsmiller, Jr., J. T. Mihalczo
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 373-381
Technical Paper | Accelerator | doi.org/10.13182/NT79-A19225
Addendum to“Impurity Radiation from Medium Density Plasmas”
G. R. Hopkins, John M. Rawls
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 382-387
Technical Note | Reactor | doi.org/10.13182/NT79-A19226
Nickel-Chromium Alloy Submerged Arc Weld Surfacing Using Metal Powder Filler Additions
G. H. Reynolds
Nuclear Technology | Volume 43 | Number 3 | May 1979 | Pages 388-390
Technical Note | Material | doi.org/10.13182/NT79-A19227
