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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Total Energy Investment in Nuclear Power Plants
Charles T. Rombough, Billy V. Koen
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 5-11
Technical Paper | Reactor | doi.org/10.13182/NT75-A24399
On the Matching of Fusion Breeders to Heavy-Water Reactors
G. LaVergne, J. E. Robinson, J. G. Martel
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 12-22
Technical Paper | Reactor | doi.org/10.13182/NT75-A24400
Fissile-Solution Storage in Pipes Isolated by Concrete or Water
S. J. Altschuler, C. L. Schuske
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 23-34
Technical Paper | Chemical Processing | doi.org/10.13182/NT75-A24401
Diffusion Analyses for Systems of Spherical Particles
Walter A. Stark, Jr.
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 35-45
Technical Paper | Material | doi.org/10.13182/NT75-A24402
Fatigue-Crack Propagation in a Cast Stainless Steel
Lee A. James
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 46-53
Technical Paper | Material | doi.org/10.13182/NT75-A24403
Benefit/Risk Analysis of Cardiac Pacemakers Powered by Betacel® Promethium-147 Batteries
T. H. Smith, J. Greenborg, W. E. Matheson
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 54-64
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24404
Computer Design of High-Explosive Experiments to Simulate Subsurface Nuclear Detonations
Donald E. Burton, Charles M. Snell, Jon B. Bryan
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 65-87
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT75-A24405
Radioactivity Trapped in Melt Produced by a Nuclear Explosion
I. Y. Borg
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 88-100
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT75-A24406
Dynamic Nondestructive Inspection Using Thermal Neutrons
Paul J. Rose, Alan M. Jacobs, Edward S. Kenney
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 101-106
Technical Paper | Analysis | doi.org/10.13182/NT75-A24407
Time-Resolved Neutron Radiography Using a Fast Pulse Reactor
C. L. Aseltine, R. A. Strich
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 107-114
Technical Paper | Technique | doi.org/10.13182/NT75-A24408
A Comprehensive Expression for the Doubling Time of Fast Breeder Reactors
R. W. Hardie, W. W. Little, R. P. Omberg
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 115-116
Technical Note | Reactor | doi.org/10.13182/NT75-A24409
New Concepts for Controlled Fusion Reactor Blanket Design
Robert W. Conn, Gerald L. Kulcinski, Halil Avci, Mohamed El-Maghrabi
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 125-145
Technical Paper | Reactor | doi.org/10.13182/NT75-A24413
Noncoherence and Two-Phase Heat Transfer in LMFBR Fuel-Coolant Interaction
P. M. Haas, C. A. Erdman, P. L. Garner, A. B. Reynolds
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 146-164
Technical Paper | Reactor | doi.org/10.13182/NT75-A24414
Fuel Vapor Generation in LMFBR Core Disruptive Accidents
A. B. Reynolds, C. A. Erdman, M. Kirbiyik
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 165-171
Technical Paper | Reactor Siting | doi.org/10.13182/NT75-A24415
Investigation of Radial Plutonium Redistribution in Mixed Oxide Fuels Irradiated in a Fast Flux
M. Bober, H. Kleykamp, G. Schumacher
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 172-182
Technical Paper | Fuel | doi.org/10.13182/NT75-A24416
Development of Brazing Filler Metals for Molybdenum
N. C. Cole, G. M. Slaughter
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 183-191
Technical Paper | Material | doi.org/10.13182/NT75-A24417
Tritium Absorption in Type 304L Stainless Steel
M. R. Louthan, Jr., J. A. Donovan, G. R. Caskey, Jr.
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 192-200
Technical Paper | Material | doi.org/10.13182/NT75-A24418
The Development of Californium-252 Sealed Sources at the Commissariat a l’Energie Atomique
P. Barthelemy, R. Berger, R. Boucher, L. Hayet
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 201-214
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24419
Effect of Separation Factors on Product Assay of an Ideal Cascade Composed of UF6 Centrifuges
Shizuo Yamashita, Tsuyoshi Okamoto
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 215-223
Technical Paper | Isotopes Separation | doi.org/10.13182/NT75-A24420
Feasibility Study of In Situ Sediment Analysis by X-Ray Fluorescence
J. A. Cooper, H. L. Nielson, N. A. Wogman, R. W. Perkins
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 224-231
Technical Paper | Analysis | doi.org/10.13182/NT75-A24421
Fabrication of Thin Uranium Dioxide Films for Neutron Flux Measurements
K. D. Feintuch, J. L. Meem
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 232-236
Technical Note | Instrument | doi.org/10.13182/NT75-A24422
Vapor Pressure Measurements of Oxide Fuel Between 3000 and 5000 K Using Laser Heating
M. Bober, H. U. Karow, K. Schretzmann
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 237-241
Technical Note | Technique | doi.org/10.13182/NT75-A24423
Simplified Small-Break Blowdown Models
L. W. Ward
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 247-253
Technical Paper | Reactor | doi.org/10.13182/NT75-A24426
Rocky Flats Experience with Borosilicate Glass Rings for Criticality Control
C. L. Schuske, J. D. McCarthy
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 254-264
Technical Paper | Chemical Processing | doi.org/10.13182/NT75-A24427
Nominally Reflected Pipe Intersections Containing Fissile Solution
Deanne Dickinson
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 265-277
Technical Paper | Chemical Processing | doi.org/10.13182/NT75-A24428
Swelling of Uranium Silicide Fuel During Postirradiation Heating
R. B. Matthews, M. L. Swanson
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 278-286
Technical Paper | Fuel | doi.org/10.13182/NT75-A24429
The Relationship Between Rupture Life and Creep Properties of Cr —1 Mo Steel
R. L. Klueh
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 287-296
Technical Paper | Material | doi.org/10.13182/NT75-A24430
Effect of Fast Reactor Fluence on Postirradiation Rupture of Type 316 Stainless Steel
A. J. Lovell
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 297-306
Technical Paper | Material | doi.org/10.13182/NT75-A24431
A Plutonium-238-Fueled Cardiac Pacemaker
Michel Alais, Rene Berger, Rene Boucher, Kenneth A. Gasper, Paul Laurens
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 307-319
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24432
Monte Carlo Dosimetry Calculation for Boron Neutron-Capture Therapy in the Treatment of Brain Tumors
Owen Leslie Deutsch, Brian Winston Murray
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 320-339
Technical Paper | Radioisotope | doi.org/10.13182/NT75-A24433
Remote Sensing of Plutonium by the Low-Energy Scattered Flux
A. E. Profio, G. C. Huth
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 340-351
Technical Paper | Analysis | doi.org/10.13182/NT75-A24434
Critical Experiments—Benchmarks (Pu-U Systems)
S. R. Bierman
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 352-381
Technical Note | Chemical Processing | doi.org/10.13182/NT75-A24435
Comparative Study of Radioactivity and Afterheat in Several Fusion Reactor Blanket Designs
R. W. Conn, T. Y. Sung, M. A. Abdou
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 391-399
Technical Paper | Reactor | doi.org/10.13182/NT75-A24440
A Fusion Design Study of Nonmobile Blankets with Low Lithium and Tritium Inventories
Mohamed A. Abdou, Layton J. Wittenberg, Charles W. Maynard
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 400-419
Technical Paper | Reactor | doi.org/10.13182/NT75-A24441
Development of High-Performance Uranium-Metal Fuels for Savannah River Reactors
W. R. McDonell, E. F. Sturcken
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 420-429
Technical Paper | Fuel | doi.org/10.13182/NT75-A24442
Effect of a Loss of Flow on a Single LMFBR-Type Fuel Pin
H. Kwast
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 430-441
Technical Paper | Fuel | doi.org/10.13182/NT75-A24443
Design of Prototype Carbide Subassemblies and an Evaluation of Proof-Testing Plans in the FFTF
J. A. Vitti, P. K. Doherty, G. F. di Lauro, J. C. Gilbertson, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 442-451
Technical Paper | Fuel | doi.org/10.13182/NT75-A24444
Safety Margins for Sodium-Bonded Carbide Fuel
E. R. Siegmann, J. C. Gilbertson
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 452-459
Technical Paper | Fuel | doi.org/10.13182/NT75-A24445
Optimum Pin Diameter for LMFBR Carbide Fuels
R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 460-471
Technical Paper | Fuel | doi.org/10.13182/NT75-A24446
Design and Manufacture of Gas Tags for FFTF Fuel and Control Assemblies
C. A. Strand, R. E. Schenter
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 472-479
Technical Paper | Fuel | doi.org/10.13182/NT75-A24447
Diffusion of Linearly Distributed Material in an Evaporating Slab
A. Sy Ong, E. E. Teixeira, R. K. Nair
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 480-485
Technical Paper | Material | doi.org/10.13182/NT75-A24448
The Influence of Fuel Microstructure on In-Pile Densification
W. Chubb, A. C. Hott, B. M. Argall, G. R. Kilp
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 486-495
Technical Paper | Material | doi.org/10.13182/NT75-A24449
Panel Discussion: Engineering Problems in Power Reactor Shielding
J. Locante, W. M. Lowder, B. A. Engholm, W. E. Kreger
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 496-507
Technical Paper | Shielding | doi.org/10.13182/NT75-A24450
Shielding Design and Analysis Methods for Pressurized Water Reactors
J. J. Sapyta, G. L. Simmons
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 508-515
Technical Paper | Shielding | doi.org/10.13182/NT75-A24451
