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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.
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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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The Reactivity Effect of a Regular Array of Empty Cylindrical Channels in a Critical System
J. T. Marti, J. P. Schneeberger
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 1-5
Technical Paper | doi.org/10.13182/NSE62-A26120
The Infinite Neutron Multiplication Constant of Homogeneous Hydrogen-Moderated 2.0 wt%-U235-Enriched Uranium
John T. Mihalczo, Victor I. Neeley
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 6-11
Technical Paper | doi.org/10.13182/NSE62-A26121
Reflected-Reactor Kinetics
Charles Erwin Cohn
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 12-17
Technical Paper | doi.org/10.13182/NSE62-A26122
The Neutron Elastic Scattering Cross Section of U233 below 20 ev
M. S. Moore, F. B. Simpson
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 18-21
Technical Paper | doi.org/10.13182/NSE62-A26123
Some New Methods of Flux Synthesis
S. Kaplan
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 22-31
Technical Paper | doi.org/10.13182/NSE62-A26124
The Direct Calculation of Diffusion Lengths and Diffusion Hardened Spectra
Gerald P. Calame
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 32-39
Technical Paper | doi.org/10.13182/NSE62-A26125
Inelastic Scattering of Cold Neutrons by Polycrystals
P. G. Khubchandani, R. R. Sharma
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 40-45
Technical Paper | doi.org/10.13182/NSE62-A26126
Boundary, Gap, and Blackness Conditions in the Cylindrical Geometry Spherical Harmonics Approximation
W. W. CLENDENIN
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 46-53
Technical Paper | doi.org/10.13182/NSE62-A26127
Void Volume Ratios During Steady State Local Boiling in Case of Constant Power Distribution
C. Hubers
Nuclear Science and Engineering | Volume 13 | Number 1 | May 1962 | Pages 54-59
Technical Paper | doi.org/10.13182/NSE62-A26128
Particle—Liquid Cocurrent Downward Flow Through a Tube with a Restricting Orfice End for Application to a Mobile Fuel Nuclear Reactor System
Wan Yong Chon, Evan C. Kovacic, Frederick G. Hammitt
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 65-74
Technical Paper | doi.org/10.13182/NSE62-A26135
Simulation of the Thermal Processes in the Reactor Core Based on an Exact Solution of the Thermal Diffusion and Heat Flow Equations
W. Ciechanowicz
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 75-79
Technical Paper | doi.org/10.13182/NSE62-A26136
Reactivity Effects Produced by Fluid Motion in a Reactor Core
Bertram Wolfe
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 80-90
Technical Paper | doi.org/10.13182/NSE62-A26137
A Simplified Dynamic Model for the Vibration Frequencies and Critical Coolant Flow Velocities for Reactor Parallel Plate Fuel Assemblies
G. S. Rosenberg, C. K. Youngdahl
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 91-102
Technical Paper | doi.org/10.13182/NSE62-A26138
Gas Chromatography as Applied to Nuclear Technology—I
A. D. Horton
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 103-109
Technical Paper | doi.org/10.13182/NSE62-A26139
An Engineering Physics Method of Calculation Applied to Light-Water Critical Experiments Investigating Nuclear Superheat
R. W. Deutsch
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 110-131
Technical Paper | doi.org/10.13182/NSE62-A26140
Theory of Resonance Absorption of Neutrons
Rubin Goldstein, E. Richard Cohen
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 132-140
Technical Paper | doi.org/10.13182/NSE62-1
The Space-Time Neutron Kinetic Equations Obtained by the Semidirect Variational Method
D. E. Dougherty, C. N. Shen
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 141-148
Technical Paper | doi.org/10.13182/NSE62-A26142
Velocity Dependent Milne's Problem
R. Kladnik, I. Kuščer
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 149-152
Technical Paper | doi.org/10.13182/NSE62-A26143
Development of the Semihomogeneous Fuel Element for a Gas-Cooled Reactor
S. A. Bernsen, H. C. Hopkins, Jr., R. C. Howard
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 153-165
Technical Paper | doi.org/10.13182/NSE62-A26144
Two Methods of Calculating Fast Reactor Control Rod Effect and Their Agreement With Experiment
A. D. Krumbein, J. H. Ray
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 166-170
Technical Paper | doi.org/10.13182/NSE62-A26145
Moments Calculations of the Fermi Age in Moderators and Moderator—Metal Mixtures
G. D. Joanou, A. J. Goodjohn, N. F. Wikner
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 171-189
Technical Paper | doi.org/10.13182/NSE62-A26146
Interaction of Adjacent Neutron Detectors
G. Ronald Dalton
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 190-196
Technical Paper | doi.org/10.13182/NSE62-A26147
The Correlation of Integral Experiments and High Energy Cross Sections
J. Chernick, H. C. Honeck, P. Michael, S. O. Moore, G. Srikantiah
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 205-214
Technical Paper | doi.org/10.13182/NSE62-A26155
The Thermalization and Diffusion of Neutrons in Heavy Gaseous Moderators
Satoru Katsuragi
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 215-229
Technical Paper | doi.org/10.13182/NSE62-A26156
Thermalization and Diffusion Parameters of Neutrons in Zirconium Hydride
J. W. Meadows, J. F. Whalen
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 230-236
Technical Paper | doi.org/10.13182/NSE62-A26157
The Behavior of Extrapolation Distances in Die-Away Experiments
E. M. Gelbard, J. A. Davis
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 237-244
Technical Paper | doi.org/10.13182/NSE62-A26158
Calorimetric Measurement of Nuclear Heating in a Reactor
C. D. Bopp, R. L. Towns
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 245-249
Technical Paper | doi.org/10.13182/NSE62-A26159
Scattering of Thermal Neutrons in the Doppler Approximation
S. N. Purohit, A. K. Rajagopal
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 250-260
Technical Paper | doi.org/10.13182/NSE62-A26160
Influence of the Moderator Size on the Slowing Down of (D, D) Neutrons in Paraffin Wax
B. Grimeland, S. Messelt, L. Sund
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 261-263
Technical Paper | doi.org/10.13182/NSE62-A26161
Measurements of Neutron Spectra with a Fast Chopper
Erik Johansson, Erik Jonsson
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 264-270
Technical Paper | doi.org/10.13182/NSE62-A26162
Frequency Response of Current Ion Chamber
R. Subramaniam, R. Vedam
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 271-274
Technical Paper | doi.org/10.13182/NSE62-A26163
Thermal Properties of Air-Cooled Graphite Channels
Donald G. Schweitzer
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 275-282
Technical Paper | doi.org/10.13182/NSE62-A26164
Heat Transfer in Sodium-Potassium Alloy
R. A. Baker, Alexander, Sesonske
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 283-288
Technical Paper | doi.org/10.13182/NSE62-A26165
Thermal Neutron Capture Cross Section and Resonance Capture Integral of Ce144
P. M. Lantz
Nuclear Science and Engineering | Volume 13 | Number 3 | July 1962 | Pages 289-294
Technical Paper | doi.org/10.13182/NSE62-A26166
Reflector Moderated Reactors
C. B. Mills
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 301-305
Technical Paper | doi.org/10.13182/NSE62-A26172
Thermal Neutron Spectra in Graphite
D. E. Parks, J. R. Beyster, N. F. Wikner
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 306-324
Technical Paper | doi.org/10.13182/NSE62-A26173
Transient Thermal Behavior of Experimental UO2 Fuel Elements in the Sodium Reactor Experiment (SRE)
J. T. Ream, R. P. Varnes
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 325-337
Technical Paper | doi.org/10.13182/NSE62-A26174
The Effect of Modal Interaction in the Xenon Instability Problem
Geza L. Gyorey
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 338-344
Technical Paper | doi.org/10.13182/NSE62-A26175
Comparison of Flux Ratio Calculations in Lattices by Integral Transport Theory
Yuzo Fukai
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 345-354
Technical Paper | doi.org/10.13182/NSE62-A26176
Fast Reactor Rocket Engines—Criticality
Ralph Cooper
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 355-365
Technical Paper | doi.org/10.13182/NSE62-A26177
A Review of the Methods Used for the Determination of Hydrogen in Uranium
Harold F. Waldron
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 366-373
Technical Paper | doi.org/10.13182/NSE62-A26178
An Improved Procedure for U235 Isotopic Ratio Analysis in Impure Materials
W. D. Kelley, B. L. Twitty
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 374-377
Technical Paper | doi.org/10.13182/NSE62-A26179
Capsule Irradiations of a Paste of Uranium—10 wt % Molybdenum Powder in NaK
E. C. Kovacic, Paul R. Huebotter, John E. Gates
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 378-384
Technical Paper | doi.org/10.13182/NSE62-A26180
Resonance and Thermal Neutron Self-Shielding in Cobalt Foils and Wires
T. A. Eastwood, R. D. Werner
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 385-390
Technical Paper | doi.org/10.13182/NSE62-A26181
Laboratory-Scale Demonstration of the Fused Salt Volatility Process
G. I. Gathers, R. L. Jolley, E. G Moncrief
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 391-397
Technical Paper | doi.org/10.13182/NSE62-A26182