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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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Timing the Utilization of Recycle Fuels in High-Temperature Gas-Cooled Reactors
F. J. Homan
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 5-15
Technical Paper | Fuel Cycle | doi.org/10.13182/NT74-A31375
Application of Amberlite Xe-270 Resin to Purification of Neptunium
Wallace W. Schulz
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 16-25
Technical Paper | Chemical Processing | doi.org/10.13182/NT74-A31376
A Comparison of Sphere-Pac and Pellet (U,Pu)O2 Fuel Pins in Low-Burnup Instrumented Irradiation Tests
R. B. Fitts, F. L. Miller
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 26-38
Technical Paper | Fuel | doi.org/10.13182/NT74-A31377
Tritium in Fusion Power Reactor Blankets
R. G. Hickman
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 39-49
Technical Paper | Material | doi.org/10.13182/NT74-A31378
Neutron Fluence and Atomic Displacement Rates for Graphite Irradiations
W. C. Morgan
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 50-56
Technical Paper | Material | doi.org/10.13182/NT74-A31379
Gamma Gauge for the Control of Interzone Layer in an Extraction Tower
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 57-66
Technical Paper | Instrument | doi.org/10.13182/NT74-A31380
Intercomparison of Nonperturbing Techniques for Inferring the Reactivity of Fast Reactors
A. R. Buhl, J. C. Robinson, E. T. Tomlinson
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 67-74
Technical Paper | Technique | doi.org/10.13182/NT74-A31381
A New Carbon-Activity Meter for High-Temperature Sodium
W. E. Ruther, S. B. Skladzien, M. F. Roche, J. W. Allen
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 75-78
Technical Note | Instrument | doi.org/10.13182/NT74-A31382
An Optimal Nuclear Fuel Management Model for Fast Reactors
H. G. Stoll, R. A. Axford
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 85-98
Technical Paper | Reactor | doi.org/10.13182/NT74-A31365
Two Interesting Phenomena Observed in the Axial Power Distribution of a BWR
T. Shimooke
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 99-110
Technical Paper | Reactor | doi.org/10.13182/NT74-A31366
Deep Self-Burial of Radioactive Wastes by Rock-Melting Capsules
Stanley E. Logan
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 111-124
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31367
A Method for Detecting Fuel Cladding Penetration in LMFBRrs by Monitoring the Sodium Coolant for Iodine-135
N. R. Chellew, W. E. Miller, R. W. Kessie, C. C. McPheeters, P. A. Nelson
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 125-132
Technical Paper | Instrument | doi.org/10.13182/NT74-A31368
Measurements of UF6 Cylinders with Portable Instruments
R. B. Walton, T. D. Reilly, J. L. Parker, J. H. Menzel, E. D. Marshall, L. W. Fields
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 133-148
Technical Paper | Instrument | doi.org/10.13182/NT74-A31369
Detection of Defective SiC Layers in Coated Nuclear Fuel Particles
D. M. Hewette, II, W. R. Laing
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 149-150
Technical Note | Fuel | doi.org/10.13182/NT74-A31370
Definitions of Breeding Ratio and Doubling Time
Harvey L. Wyckoff, Paul Greebler
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 158-164
Technical Paper | Reactor | doi.org/10.13182/NT74-A31387
Practical Xenon Spatial Control
Douglas C. Bauer, Claude G. Poncelet
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 165-189
Technical Paper | Reactor | doi.org/10.13182/NT74-A31388
Civil Defense Implications of an LMFBR in a Thermonuclear Target Area
C. V. Chester, R. O. Chester
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 190-200
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A31389
Two Fusion Reactor Blankets with Vanadium as Structural Material
James E. Struve, Nick Tsoulfanidis
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 201-207
Technical Paper | Material | doi.org/10.13182/NT74-A31390
In-Pile Thermal Conductivity of Fuel Oxide: UO2 Pellets and Vipac UO2-PuO2 Pellets and Sol-Gel
A. Calza-Bini, G. Cosoli, G. Filacchioni, M. Lanchi, A. Nobili, U. Rocca, P. L. Rotoloni
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 208-216
Technical Paper | Material | doi.org/10.13182/NT74-A31391
Calibration Stability of Oxygen Meters for LMFBR Sodium Systems
J. M. McKee, D. R. Vissers, P. A. Nelson, B. R. Grundy, E. Berkey, G. R. Taylor
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 217-227
Technical Paper | Material | doi.org/10.13182/NT74-A31392
The Utilization of On-Line Monitors at EBR-II for Sodium Purity
John T. Holmes, Grant O. Haroldsen
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 228-234
Technical Paper | Instrument | doi.org/10.13182/NT74-A31393
A Hydrogen-Activity Meter for Liquid Sodium and its Application to Hydrogen Solubility Measurements
D. R. Vissers, J. T. Holmes, L. G. Bartholme, P. A. Nelson
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 235-244
Technical Paper | Instrument | doi.org/10.13182/NT74-A31394
