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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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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