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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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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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Use of Zero Power Plutonium Reactor Measurements as a Support of Criticality Prediction for the SNR-300
S. Pilate, R. de Wouters, U. Wehmann, F. Helm, W. Scholtyssek
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 5-11
Technical Paper | Reactor | doi.org/10.13182/NT78-A32128
Tritium Pathways and Handling Problems in a Laser Fusion Reactor
Edwin M. Larsen, S. I. Abdel-Khalik, Mark S. Ortman
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 12-26
Technical Paper | Reactor | doi.org/10.13182/NT78-A32129
Improved Load Follow Strategy for Return-to-Power Capability
C. E. Meyer, C. L. Bennett, D. J. Hill, K. J. Dzikowski
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 27-35
Technical Paper | Reactor | doi.org/10.13182/NT78-A32130
A Generalized Treatment of Heterogeneity Effects for the Shielding Factor Method
E. Kujawski, R. Protsik
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 36-45
Technical Paper | Reactor | doi.org/10.13182/NT78-A32131
Denatured Fuel Cycles for International Safeguards
T. H. Pigford, C. S. Yang, M. Maeda
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 46-59
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32132
Actinide Redistribution in the Outer Regions of Mixed-Oxide Fuel
L. A. Lawrence, D. C. Hata, D. F. Washburn
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 60-70
Technical Paper | Fuel | doi.org/10.13182/NT78-A32133
Radiation Shielding of Major Penetrations in Tokamak Reactors
Jungchung Jung, Mohamed A. Abdou
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 71-86
Technical Paper | Shielding | doi.org/10.13182/NT78-A32134
Calculation of Spatial Weighting Functions for Ex-Core Neutron Detectors
Mark W. Crump, John C. Lee
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 87-96
Technical Paper | Instrument | doi.org/10.13182/NT78-A32135
Reliability, Reliability with Repair, and Availability of Four Identical Element Multiplex Systems
Richard D. Guild, Edmond G. Tourigny
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 97-108
Technical Paper | Technique | doi.org/10.13182/NT78-A32136
Development and Testing of Neutron Dosimetry Techniques for Accelerator-Based Irradiation Facilities
L. R. Greenwood, R. R. Heinrich, R. J. Kennerley, R. Medrzychowski+
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 109-128
Technical Paper | Technique | doi.org/10.13182/NT78-A32137
The Effect of Drop Evaporation Rate on Containment Pressure Transients
Kazys K. Almenas, Joseph M. Marchello
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 263-275
Technical Paper | Reactor | doi.org/10.13182/NT78-A32112
An Assessment of the Consequences of Boiling in the Radial Blanket due to Hypothetical Major Pipe Leaks
N. Prasad Kadambi, Roger W. Tilbrook
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 276-282
Technical Paper | Reactor | doi.org/10.13182/NT78-A32113
A Space-Time Analysis of Void Reactivity Feedback in Boiling Water Reactors
Hsiang-Shou Cheng, Ming-Shih Lu, David J. Diamond
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 283-298
Technical Paper | Reactor | doi.org/10.13182/NT78-A32114
Sputtering Erosion in Inertial Confinement Fusion Reactors
I. O. Bohachevsky, J. F. Hafer
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 299-311
Technical Paper | Reactor | doi.org/10.13182/NT78-A32115
An SAS3D Analysis of Unprotected Loss-of-Flow Transients for 1200-MW(electric) Liquid-Metal Fast Breeder Reactor Homogeneous and Heterogeneous Core Designs
T. A. Shih, M. I. Temme
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 312-322
Technical Paper | Reactor | doi.org/10.13182/NT78-A32116
Extraction of Actinide Elements by Trilaurylammonium Nitrate Carboxylic Acid Mixtures and Applications
Charles Madic, Gerard Koehly
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 323-340
Technical Paper | Chemical Processing | doi.org/10.13182/NT78-A32117
Safety Calculations and Benchmarking of Babcock and Wilcox Designed Close Spaced Fuel Storage Racks
William D. Bromley, James S. Olszewski
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 341-348
Technical Paper | Chemical Processing | doi.org/10.13182/NT78-A32118
Response of Oxide Fuel to Simulated Thermal Transients
G. Bandyopadhyay
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 349-358
Technical Paper | Fuel | doi.org/10.13182/NT78-A32119
Tensile Properties and Annealing Characteristics of H. B. Robinson Spent Fuel Cladding
A. A. Bauer, L. M. Lowry
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 359-372
Technical Paper | Fuel | doi.org/10.13182/NT78-A32120
Microstructures and Leachability of Vitrified Radioactive Wastes
W. N. Rankin, J. A. Kelley
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 373-380
Technical Paper | Radioactive Waste | doi.org/10.13182/NT78-A32121
A Generic Hazard Evaluation of Low-Level Waste Burial Grounds
B. L. Cohen, H. N. Jow
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 381-388
Technical Paper | Radioactive Waste | doi.org/10.13182/NT78-A32122
Minimizing Radioactivity and Other Features of Elemental and Isotopic Tailoring of Materials for Fusion Reactors
Robert W. Conn, Kevin Okula, A. Wayne Johnson
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 389-400
Technical Paper | Material | doi.org/10.13182/NT78-A32123
Application of Reactivity Weighting to Rod Ejection Accident Analysis in a Pressurized Water Reactor
S. Bian
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 401-407
Technical Note | Reactor | doi.org/10.13182/NT78-A32124
Swelling in Mixed-Oxide Fuel Pins
H. Zimmermann
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 408-410
Technical Note | Fuel | doi.org/10.13182/NT78-A32125
A Low-Decontamination Approach to a Proliferation-Resistant Fuel Cycle
J. G. Asquith, L. F. Grantham
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 137-148
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32100
Coprocessing—An Evaluation of Chemical Reprocessing Without Plutonium Separation
Meyer Pobereskin, Kenneth D. Kok, William J. Madia
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 149-167
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32101
Some Plutonium Recycle Program Fuel Cycles Having Reduced Proliferation Characteristics
Eugene A. Eschbach
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 168-179
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32102
An Investigation of Altered Transverse Transport of Axial Momentum in Coolant Flows During Oscillatory Instabilities
R. P. Roy, P. K. Jain
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 180-184
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32103
Investigations of Anticipated Transients Without Reactor Scram and Other Selected Safety Devices
W. Ullrich, W. Frisch
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 185-194
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32104
Enrichment Zoning and Control Rod Programming for Reactivity and Power Shape Control
Constantine P. Tzanos
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 195-206
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32105
Benchmark Critical Experiments on High-Enriched Uranyl Nitrate Solution Systems
Robert E. Rothe, Inki Oh
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 207-225
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32106
A Calculational Study of Benchmark Critical Experiments on High-Enriched Uranyl Nitrate Solution Systems
Inki Oh, Robert E. Rothe
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 226-243
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32107
Uranium Requirements for Advanced Fuel Cycles in Expanding Nuclear Power Systems
S. Banerjee, H. Tamm
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 244-251
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32108
Analyzing Containment Leakage from a Sodium Fire by the Response Surface Method
Lucy W. Person
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 252-256
Technical Note | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32109
