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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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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
