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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
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Fission Gas Release and Swelling During Heating of Irradiated EBR-II Type Fuel
N. R. CHELLEW, R. K. STEUNENBERG
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE62-A26192
Determination of Fission Product Background in the Gamma Coincidence Technique for U238 Activation Measurements
HECTOR M. ANTÚNEZ
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 8-10
Technical Paper | doi.org/10.13182/NSE62-A26193
Resonance and Total U238 Activation in Thin Natural Uranium-Niobium Fuel Plates
J. J. KEPES, L. A. MIKOLEIT, R. G. SERENKA
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 11-16
Technical Paper | doi.org/10.13182/NSE62-A26194
Penetration and Diffusion of a Beam of Radiation
WILLIAM R. FAUST, ARLO D. ANDERSON
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 17-21
Technical Paper | doi.org/10.13182/NSE62-A26195
Two Group Reactor Kinetics
A. FODERARO, H. L. GARABEDIAN
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 22-29
Technical Paper | doi.org/10.13182/NSE62-A26196
In-Pile Photographic Studies of EBR-II Mark-I and Fermi Core—A Sample Meltdown
C. E. DICKERMAN, G. H. GOLDEN, L. E. ROBINSON
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 30-36
Technical Paper | doi.org/10.13182/NSE62-A26197
Design and Analysis of the Experimental Gas-Cooled Reactor Fuel Assemblies
G. SAMUELS
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 37-52
Technical Paper | doi.org/10.13182/NSE62-A26198
Materials Development for Core I Fuel Assemblies for the Experimental Gas-Cooled Reactor
J. H. COOBS
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 53-68
Technical Paper | doi.org/10.13182/NSE62-A26199
Irradiation Testing of Fuel Materials for EGCR
D. B. TRAUGER
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 69-82
Technical Paper | doi.org/10.13182/NSE62-A26200
Irradiation Effects in the EGCR Fuel
J. G. MORGAN, M. F. OSBORNE, O. SISMAN
Nuclear Science and Engineering | Volume 14 | Number 1 | September 1962 | Pages 83-100
Technical Paper | doi.org/10.13182/NSE62-A26201
The Development of High Purity Tantalum and Alloys for Liquid Plutonium Containment in LAMPRE I
Richard M. Bidwell, William E. Ferguson, Calvin C. Burwell, R. Philip Hammond, Keith V. Davidson, Walter R. Wykoff, Robert W. Anderson
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 109-122
Technical Paper | doi.org/10.13182/NSE62-A28110
Corrosion Testing and Fuel Selection for LAMPRE I
C. C. Burwell, R. M. Bidwell, R. P. Hammond, J. E. Kemme, and B. J. Thamer
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 123-134
Technical Paper | doi.org/10.13182/NSE62-A28111
Fabrication of Tantalum Fuel Containers for the LAMPRE I Molten Plutonium Reactor
G. S. Hanks, R. S. Kirby, J. M. Taub
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 135-143
Technical Paper | doi.org/10.13182/NSE62-A28112
Fit of Yankee Startup Experiment Data to a Simple Reactor Analysis Model
Wm. Howard Arnold, Jr.
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 144-152
Technical Paper | doi.org/10.13182/NSE62-A28113
The Measurement of Dynamic Nuclear Reactor Parameters Using the Variance of the Number of Neutrons Detected
Robert W. Albrecht
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 153-158
Technical Paper | doi.org/10.13182/NSE62-A28114
Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate-Hydrocarbon Diluent Solutions: I. Distribution Studies with TBP in Amsco 125-82 at Intermediate and Low Acidities
Wallace Davis, Jr.
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 159-168
Technical Paper | doi.org/10.13182/NSE62-A28115
Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate-Hydrocarbon Diluent Solutions: II. Densities, Molar Volumes, and Water Solubilities of TBP-Amsco 125-82-HNO3-H2O Solutions
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 169-173
Technical Paper | doi.org/10.13182/NSE62-A28116
Thermodynamics of Extraction of Nitric Acid by Tri-n-Butyl Phosphate—Hydrocarbon Diluent Solutions: III. Comparison of Literature Data
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 174-178
Technical Paper | doi.org/10.13182/NSE62-A28117
Determination of Diffusion Coefficients for Thermal Neutrons in D2O at 20, 100, 165, and 220°C
Norman P. Baumann
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 179-185
Technical Paper | doi.org/10.13182/NSE62-A28118
Radiation of an Extended Source
M. J. Barrett
Nuclear Science and Engineering | Volume 14 | Number 2 | October 1962 | Pages 186-191
Technical Paper | doi.org/10.13182/NSE62-A28119
Cavitation and Erosion Damage and Damage Particle-Size Measurements with Radioisotopes
William J. Walsh, Frederick G. Hammitt
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 217-223
doi.org/10.13182/NSE62-A26209
Determination of Diffusion Hardening in Water
Eugene Starr, Juan Koppel
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 224-229
doi.org/10.13182/NSE62-A26210
Uranium Powder Ignition Studies
Marvin Tetenbaum, Larry Mishler, Glenn Schnizlein
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 230-238
doi.org/10.13182/NSE62-A26211
The Dancoff Correction in Gap Geometry
W. Rothenstein J. Helholtz
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 239-243
doi.org/10.13182/NSE62-A26212
Resonance Absorption of Neutrons In Lumps with Nonuniform Temperature Distributions
Joel H. Ferziger
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 244-248
doi.org/10.13182/NSE62-A26213
Coincidence Counting of Special Samples
R. F. Overman
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 249-253
doi.org/10.13182/NSE62-A26214
Diffusion Anisotropy in Singly- and Doubly-Periodic Lattices
J. R. Beeler
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 254-265
doi.org/10.13182/NSE62-A26215
An Analytic Approach to Two-Dimensional Reactor Theory
H. L. Garabedian, D. H. Thomas
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 266-271
doi.org/10.13182/NSE62-A26216
A Digital Computer Analysis of Loss-of-Coolant Accident for a Multicircuit Core Nuclear Power Plant
Amir N. Nahavandi
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 272-286
doi.org/10.13182/NSE62-A26217
The Mechanism of Extraction by Tributyl Phosphate—n-Hexane Solvents: Part I. Water Extraction
Donald R. Olander, Manson Benedict
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 287-294
doi.org/10.13182/NSE62-A26218
Discrete Ordinate Quadratures for Thin Slab Cells
David Meneghetti
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 295-303
doi.org/10.13182/NSE62-A26219
Analysis of the Sodium Reactor Experiment Prompt Power Coefficient
C. W. Griffin
Nuclear Science and Engineering | Volume 14 | Number 3 | November 1962 | Pages 304-311
doi.org/10.13182/NSE62-A26220
Measurement of Void Fractions in Parallel Rod Arrays
Richard A. Condon, Neil C. Sher
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 327-338
Technical Paper | doi.org/10.13182/NSE62-A26239
The Effect of Rotational Freedom in Several Ammonium Salts and Dimethyl Acetylene on the Inelastic Scattering of Slow Neutrons
J. J. Rush, G. J. Safford, T. I. Taylor, W. W. Havens, Jr.
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 339-345
Technical Paper | doi.org/10.13182/NSE62-A26240
Renewal Theory and the Slowing Down of Neutrons
Coleridge A. Wilkins
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 346-357
Technical Paper | doi.org/10.13182/NSE62-A26241
The Effective U238 Resonance Capture Integrals of Uranium Metal and UO2 Rods
J. Hardy, Jr., G. G. Smith, D. Klein
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 358-365
Technical Paper | doi.org/10.13182/NSE62-A26242
Some Experimental Results Pertinent to Equivalence Relations for Effective Resonance Integrals
J. Hardy, Jr., D. Klein, G. G. Smith
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 366-370
Technical Paper | doi.org/10.13182/NSE62-A26243
Closed Loop Dynamics of Nuclear Rocket Engines with Bleed Turbine Drive
Harold P. Smith, Jr.
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 371-379
Technical Paper | doi.org/10.13182/NSE62-A26244
Mean-Square Error Minimization of Boiling Reactor Noise
Lynn E. Weaver, Kenneth R. Katsma
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 380-383
Technical Paper | doi.org/10.13182/NSE62-A26245
Comparative Performance of Black vs. Gray Control Rods in the Engineering Test Reactor
E. E. Burdick, D. G. Proctor
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 384-389
Technical Paper | doi.org/10.13182/NSE62-A26246
Resonance Absorption in Materials with Grain Structure
R. K. Lane, L. W. Nordheim, J. B. Sampson
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 390-396
Technical Paper | doi.org/10.13182/NSE62-A26247
Neutron Diffractometer Measurement of the Slow Neutron Spectrum from a Modified Split Reactor Core
G. A. Ferguson, Jr., R. H. VOgt
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 397-400
Technical Paper | doi.org/10.13182/NSE62-A26248
A Generalized Variational Method for Reactor Analysis
Alfred L. Mowery, Jr., Raymond L. Murray
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 401-413
Technical Paper | doi.org/10.13182/NSE62-A26249
Void Measurement by the (γ, n) Reaction
S. Zia Rouhani
Nuclear Science and Engineering | Volume 14 | Number 4 | December 1962 | Pages 414-419
Technical Paper | doi.org/10.13182/NSE62-A26250