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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
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Summary of the ALARA Nature of Design Effluents from the Clinch River Breeder Reactor Plant
Kenneth L. Ferguson
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 5-12
Technical Paper | Reactor | doi.org/10.13182/NT79-A32157
Assessment of Criticality Safety
R. C. Lloyd, S. W. Heaberlin, E. D. Clayton, R. D. Carter
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 13-21
Technical Paper | Reactor | doi.org/10.13182/NT79-A32158
A Parametric Study of a Lithium-Cooled Tokamak Blanket
J. Chao, B. B. Mikic, N. E. Todreas
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 22-33
Technical Paper | Reactor | doi.org/10.13182/NT79-A32159
Preliminary Design and Neutronic Analysis of a Laser Fusion Driven Actinide Waste Burning Hybrid Reactor
D. H. Berwald, J. J. Duderstadt
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 34-50
Technical Paper | Reactor | doi.org/10.13182/NT79-A32160
Decision Table Development and Application to the Construction of Fault Trees
S. L. Salem, J. S. Wu, G. Apostolakis
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 51-64
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32161
Proposed Extension of Raschig Ring Standard to Low Enriched Uranium Fuels
N. Ketzlach
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 65-70
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A32162
Proton Simulation of Irradiation-Induced Creep
E. K. Opperman, J. L. Straalsund, G. L. Wire, R. H. Howell
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 71-81
Technical Paper | Material | doi.org/10.13182/NT79-A32163
Low Cycle Fatigue Behavior of Types 304 and 316 Stainless Steel Tested in Sodium at 550°C
G. J. Zeman, D. L. Smith
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 82-89
Technical Paper | Material | doi.org/10.13182/NT79-A32164
Garden Hose Separation of Gaseous Isotopes. Part II: Supersonic Accelerations
Chia-Gee Wang, Anthony G. M. Davis
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 90-101
Technical Paper | Isotopes Separation | doi.org/10.13182/NT79-A32165
A Solvent Extraction-Liquid Scintillation Method for Assay of Uranium and Thorium in Phosphate-Containing Material
Edward J. Bouwer, John W. McKlveen, W. J. McDowell
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 102-111
Technical Paper | Analysis | doi.org/10.13182/NT79-A32166
Authors
D. R. Haffner, R. W. Hardie, D. R. Marr, D. A. Cantley, J. C. Chandler, D. C. McCurry, R. P. Omberg, Carol A. Sege, Saul Strauch, Ronald P. Omberg, Irving Spiewak, D. J. Pellarin, J. L. Jarriel, P. Chr. Løken, J. Bakke, I. Gløersen, Paul Naefe, Erich Zimmer, Kenji Motojima, Enzo Tachikawa, Hideo Kamiyama, T. A. Parish, L. A. Lawrence, D. C. Hata, J. W. Weber, C. T. Walker, S. Pickering, Eugen Wild, Klaus J. Mack
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 119-122
Department | Thorium Fuel Cycle in a Breeder Economy | doi.org/10.13182/NT79-A32141
Reactor Physics Parameters of Alternate Fueled Fast Breeder Reactor Core Designs
D. R. Haffner, R. W. Hardie
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 123-132
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Fuel Cycle | doi.org/10.13182/NT79-A32142
Performance of Thorium-Fueled Fast Breeders
D. R. Marr, D. A. Cantley, J. C. Chandler, D. C. McCurry, R. P. Omberg
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 133-143
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Fuel Cycle | doi.org/10.13182/NT79-A32143
The Denatured Thorium Cycle—An Overview
Carol A. Sege, Saul Strauch, Ronald P. Omberg, Irving Spiewak
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 144-149
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Reactor | doi.org/10.13182/NT79-A32144
Pulsed Reactivity Measurements of Large 235U-AI Castings in H2O
D. J. Pellarin, J. L. Jarriel
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 150-154
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Reactor | doi.org/10.13182/NT79-A32145
Rock Cavity Construction of a Nuclear Power Plant—A Case Study
P. Chr. Løken, J. Bakke, I. Gløersen
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 155-162
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Reactor Siting | doi.org/10.13182/NT79-A32146
Preparation of Uranium Kernels by an External Gelation Process
Paul Naefe, Erich Zimmer
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 163-171
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Chemical Processing | doi.org/10.13182/NT79-A32147
Removal of Radiocobalt Ion in Waste Water by Oxine-Impregnated Activated Charcoal. Part II: Column Experiments
Kenji Motojima, Enzo Tachikawa, Hideo Kamiyama
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 172-179
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Chemical Processing | doi.org/10.13182/NT79-A32148
A Neutronic Assessment of Strontium-90 Transmutation in Fusion Reactors
T. A. Parish
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 180-194
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Radioactive Waste | doi.org/10.13182/NT79-A32149
The Effects of Stoichiometry on Cladding Attack in UO2-PuO2
L. A. Lawrence, D. C. Hata, J. W. Weber
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 195-206
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32150
Some Electron Microprobe Analysis Results Concerning the Interaction Between Uranium-Plutonium Mixed-Oxide Fuel and Stainless-Steel Cladding
C. T. Walker, S. Pickering
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 207-215
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32151
Experimental Parameter Investigations on the Tribological Behavior of Stellite 6 in Liquid Sodium
Eugen Wild, Klaus J. Mack
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 216-223
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32152
Critical Separation Between Subcritical Clusters of Low Enriched UO2 Rods in Water with Fixed Neutron Poisons
S. R. Bierman, B. M. Durst, E. D. Clayton
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 237-249
Technical Paper | Reactor | doi.org/10.13182/NT79-A32178
Intercomparison of Auto- and Cross-Power Spectral Density Surveillance Systems for Sodium Boiling Detection in Fast Reactors
Joachim Ehrhardt
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 250-263
Technical Paper | Reactor | doi.org/10.13182/NT79-A32179
Characterization of Fragmented Fuel from a Thermal Fuel-Sodium Interaction
S. Gross, D. Vollath
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 264-271
Technical Paper | Reactor | doi.org/10.13182/NT79-A32180
Hydrogen Transport in a Toroidal Plasma Using Multigroup Discrete-Ordinates Methodology
B. R. Wienke, W. F. Miller, Jr., T. J. Seed
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 272-288
Technical Paper | Reactor | doi.org/10.13182/NT79-A32181
Loss-of-Coolant Accidents in Small Compact Nuclear Reactors
R. C. Sanders, G. E. Mueller
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 289-296
Technical Paper | Reactor Siting | doi.org/10.13182/NT79-A32182
Tracer Techniques for the Input Accountability of Plutonium in Reprocessing Plants: Magtrap and Leadtrap
C. K. Mathews, H. C. Jain, V. D. Kavimandan, S. K. Aggarwal
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 297-303
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A32183
Some Calculations of the Failure Statistics of Coated Fuel Particles
David G. Martin
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 304-311
Technical Paper | Fuel | doi.org/10.13182/NT79-A32184
Tritium Permeation Through Fe-2¼Cr-1 Mo Steam Generator Material
Terrence A. Renner, Donald J. Raue
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 312-319
Technical Paper | Material | doi.org/10.13182/NT79-A32185
Filtration of Sodium-Fire Aerosols
A. Alexas, S. Jordan, W. Lindner
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 320-323
Technical Paper | Material | doi.org/10.13182/NT79-A32186
The Effect of Axial Stress on the Transient Mechanical Response of 20% Cold-Worked Type 316 Stainless-Steel Cladding
H. Yamada
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 324-331
Technical Paper | Material | doi.org/10.13182/NT79-A32187
Calculation of the Influence of the Radial Temperature Gradient on Cladding Dilatation
D. I. R. Norris
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 332-334
Technical Paper | Material | doi.org/10.13182/NT79-A32188
Arguments Concerning the Evaluation of Cladding Dilatation due to Thermodiffusion
H. Venker, M. Bober, G. Schumacher
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Page 335
Department | Letter to the Editor | doi.org/10.13182/NT79-A32189
The Mass Spectrometric Determination of Uranium-235 in Uranium Hexafluoride
W. Beyrich, G. Spannagel
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 337-342
Technical Paper | Analysis | doi.org/10.13182/NT79-A32190
Neutron Fluence Measurements with Solid-State Nuclear Track Detectors: Results of a Comparative Study with Gold and Indium Foils
A. Aframian
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 343-349
Technical Paper | Technique | doi.org/10.13182/NT79-A32191
Bubble Worth Variation in Molten Cores from a Hypothetical Core Disruptive Acident
Charles R. Marotta
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 350-352
Technical Note | Reactor | doi.org/10.13182/NT79-A32192
Radiological Implications of Plutonium Recycle and the use of Thorium Fuels in Thermal Power Reactor Operations
H. F. MacDonald, S. Nair
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 353-361
Technical Note | Fuel Cycle | doi.org/10.13182/NT79-A32193