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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
August 2025
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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
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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