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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
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Fatigue Design Basis for Zircaloy Components
W. J. O'Donnell, B. F. Langer
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE64-A19269
Processing of Graphite Reactor Fuels Containing Coated Particles and Ceramics
R. E. Blanco, G. I. Cathers, L. M. Ferris, T. A. Gens, R. W. Horton, E. L. Nicholson
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 13-22
Technical Paper | doi.org/10.13182/NSE64-A19270
A New Liquid Scintillator for Thermal Neutron Detection
H. H. Ross, R. E. Yerick
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 23-27
Technical Paper | doi.org/10.13182/NSE64-A19271
Laminar, Turbulent, and Transition Gas Flow in Porous Media
E. Creutz
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 28-44
Technical Paper | doi.org/10.13182/NSE64-A19272
Thermally Induced Vibrations of Concentric Thin Spherical Shells
Arthur L. Austin
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 45-52
Technical Paper | doi.org/10.13182/NSE64-A19273
Spatial-Distribution Functions for Calculating Neutron Densities by Monte Carlo
Harvey J. Amster, Wilson K. Talley
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 53-59
Technical Paper | doi.org/10.13182/NSE64-A19274
Prompt-Neutron Lifetime in Critical Enriched-Uranium Metal Cylinders and Annuli
John T. Mihalczo
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 60-65
Technical Paper | doi.org/10.13182/NSE20-60
Point-to-Point Kernel Analysis of an Experiment to Determine Wall Penetration of a Squarebased Concrete Structure by Gamma Radiation
R. E. Rexroad, M. A. Schmoke H. J. Tiller, A. Foderaro, L. Degelman, G. Kowal
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 66-79
Technical Paper | doi.org/10.13182/NSE64-A19276
Ratio of Capture to Fission in U235 at keV Neutron Energies
L. W. Weston, G. de Saussure, R. Gwin
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 80-87
Technical Paper | doi.org/10.13182/NSE64-A19277
The Milne Problem in a Finite Domain I: Isotropic Scattering
F. A. Hinchey, E. A. Dean, J. B. Pearce
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 88-92
Technical Paper | doi.org/10.13182/NSE64-A19278
Transport-Theory Calculations of Temperature Coefficients in Heterogeneous Reactor Lattices
John E. Suich, Henry C. Honeck
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 93-110
Technical Paper | doi.org/10.13182/NSE64-A19279
PN Calculations
G. R. Dalton
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 131-137
Technical Paper | doi.org/10.13182/NSE64-A28926
An Absolute Thermal-Neutron-Flux Standard
R. G. Cochran, D. E. Feltz, J. D. Randall, J. V. Walker
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 138-141
Technical Paper | doi.org/10.13182/NSE64-A28927
Measurements of Conversion Ratio, Resonance Escape and Fast Fission as Student Experiments
D. A. Daavettila
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 142-150
Technical Paper | doi.org/10.13182/NSE64-A28928
Properties of Ceramic-Coated Nuclear-Fuel Particles
J. M. Blocker, Jr., M. F. Browning, W. J. Wilson, V. M. Secrest, A. C. Secrest, R. B. Landrigan, J. H. Oxley
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 153-170
Technical Paper | doi.org/10.13182/NSE64-A28930
Irradiation Studies of Ceramic-Coated Nuclear Fuel Particles
Charles W. Townley, Neil E. Miller, Robert L. Ritzman, Richard J. Burian
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 171-179
Technical Paper | doi.org/10.13182/NSE64-A28931
Development of Fueled Graphite Containing Pyrolytic-Carbon-Coated Carbide Particles for Non-purged, Gas-Cooled Reactor Systems
F. L. Carlsen, Jr., E. S. Bomar, W. O. Harms
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 180-200
Technical Paper | doi.org/10.13182/NSE64-A28932
Development and Utilization of Pyrolytic-Carbon-Coated Carbide Fuel for the High-Temperature Gas-Cooled Reactor
Walter V. Goeddel
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 201-218
Technical Paper | doi.org/10.13182/NSE64-A28933
Duplex Carbon-Coated Fuel Particles
R. A. Reuter
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 219-226
Technical Paper | doi.org/10.13182/NSE64-A28934
The Development of Spherical Pyrolytic-Carbon-Coated UC2 and UThC2 Fuel Particles
H. G. Sowman, R. L. Surver, J. R. Johnson
Nuclear Science and Engineering | Volume 20 | Number 2 | October 1964 | Pages 227-234
Technical Paper | doi.org/10.13182/NSE64-A28935
A Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide
I. E. Knudsen, H. E. Hootman and N. M. Levitz
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 259-265
Technical Paper | doi.org/10.13182/NSE64-A19567
Material Buckling and Critical Masses of Uranium Rods Containing 3 wt % U235 in H20
W. B. Rogers, Jr. and F. E. Kinard
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 266-271
Technical Paper | doi.org/10.13182/NSE64-A19568
Fast-Spectrum Doppler Measurements - Part II: A Measurement of a Negative Doppler Effect in U235 and New Measurements in Th232 and U238
T. H. Springer, S. G. Carpenter and R. J. Tuttle
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 272-280
Technical Paper | doi.org/10.13182/NSE64-A19569
Fast-Neutron Spectroscopy in a Pool-Type Reactor with Activation Detectors
G. Ben-David, E. Nardi and M. Pasternak
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 281-289
Technical Paper | doi.org/10.13182/NSE64-A19570
A Simple, Compact Rod Drive Using a Stepping Motor
Edward F. Groh and Charles E. Cohn
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 290-297
Technical Paper | doi.org/10.13182/NSE64-A19571
Neutron-Capture Cross Section of 35-h Rh105
L. E. Glendenin and R. A. Schmitt
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 298-301
Technical Paper | doi.org/10.13182/NSE64-A19572
Thermal-Neutron Capture Cross Section and Resonance Capture Integral of Ce140 and Effective Capture Cross Section of Ce141
P. M. Lantz, C. R. Baldock and L. E. Idom
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 302-306
Technical Paper | doi.org/10.13182/NSE64-A19573
Application of a Simple, Practical Method for Computing Interaction to Arrays Found Experimentally to be Critical
Hugh K. Clark
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 307-313
Technical Paper | doi.org/10.13182/NSE64-A19574
Thermal-Neutron Transmission Through Plane Cadmium Covers
J. A. DeJuren and R. K. Paschall
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 314-317
Technical Paper | doi.org/10.13182/NSE64-A19575
Optimum Reactor Shutdown Program for Minimum Xenon Buildup
Zoltan R. Rosztoczy and Lynn E. Weaver
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 318-323
Technical Paper | doi.org/10.13182/NSE64-A19576
The Even-Order Spherical-Harmonics Method in Cylindrical Geometry
John O. Mingle
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 324-330
Technical Paper | doi.org/10.13182/NSE64-A19577
Intermediate Resonance Absorption in Nonhomogeneous Systems
Rubin Goldstein and Harvey Brooks
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 331-337
Technical Paper | doi.org/10.13182/NSE64-A19578
The Application of Inhour Modes to the Description of Non-Separable Reactor Transients
A. F. Henry
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 338-351
Technical Paper | doi.org/10.13182/NSE64-A19579
Non-l/ν Thermalization Parameters for the Mass-1 and Nelkin Scattering Kernels
Gerald P. Calame
Nuclear Science and Engineering | Volume 20 | Number 3 | November 1964 | Pages 352-357
Technical Paper | doi.org/10.13182/NSE64-A19580
Detection of Gunpowder Residues by Neutron Activation Analysis
R. R. Ruch, V. P. Guinn, R. H. Pinker
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 381-385
Technical Paper | doi.org/10.13182/NSE64-A20980
Measurement of Free Fission-Gas Pressure in Operating UO2-Filled Fuel Rods
Myron B. Reynolds
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 386-391
Technical Paper | doi.org/10.13182/NSE64-A20981
A Space-Dependent Dynamic Analysis of Boiling Water Reactor Systems
Amir N. Nahavandi, Richard F. von Hollen
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 392-413
Technical Paper | doi.org/10.13182/NSE64-A20982
Thermal-Neutron Space-Time Decay Constants in Various Order PN Approximations
A. Travelli, Gerald P. Calame
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 414-427
Technical Paper | doi.org/10.13182/NSE64-A20983
Time-Dependent Flux in Small Assemblies
F. D. Judge, P. B. Daitch
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 428-435
Technical Paper | doi.org/10.13182/NSE64-A20984
The Age of Fission Neutrons to Indium-Resonance Energy in Water
R. K. Paschall
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 436-444
Technical Paper | doi.org/10.13182/NSE64-A20985
The Age of Fission Neutrons to Indium-Resonance Energy in Graphite
R. W. Campbell, R. K. Paschall, V. A. Swanson
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 445-454
Technical Paper | doi.org/10.13182/NSE64-A20986
A Thermal Neutron Extrapolation Length Measurement
Edward E. Carroll, Jr., Robert W. Stooksberry
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 455-461
Technical Paper | doi.org/10.13182/NSE64-A20987
Transport Solution of the One-Speed Slab Albedo Problem
N. J. McCormick, M. R. Mendelson
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 462-467
Technical Paper | doi.org/10.13182/NSE64-A20988
A Double-Iteration Method for Determination of Diffusion Length
Richard E. Kaiser, William R. Kimel
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 468-475
Technical Paper | doi.org/10.13182/NSE64-A20989
A Determination of the Cadmium Absorption of Resonance Neutrons in Cadmium-Covered Indium Foils
J. E. Powell, J. V. Walker
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 476-480
Technical Paper | doi.org/10.13182/NSE64-A20990
The Effect of Flux Anisotropy on Neutron-Detector Foils
G. R. Dalton, R. K. Osborn
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 481-492
Technical Paper | doi.org/10.13182/NSE64-A20991
Limitations in the Orthonormal Expansion of Neutron Spectra with Activation Measurements
Raymond Gold
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 493-512
Technical Paper | doi.org/10.13182/NSE64-A20992
Anisotropic Scattering in the SN Method
P. F. Zweifel, S. B. Garg
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 513-516
Technical Paper | doi.org/10.13182/NSE64-A20993
Time-Dependent Variational Principles for Nonconservative Systems
Jeffrey Lewins
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 517-520
Technical Paper | doi.org/10.13182/NSE64-A20994
Wear Rates in Automotive Engines by Liquid Scintillation Counting of Fe55
H. H. Ross, R. P. Gardner, J. W. Dunn, III
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 521-526
Technical Paper | doi.org/10.13182/NSE64-A20995
of U238 from 1.5 to 15 MeV
I. Asplund-Nilsson, H. Condé, N. Starfelt
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 527-535
Technical Paper | doi.org/10.13182/NSE64-A20996
Radiation and Creep Analysis for Strain Stress Distributions in Tubular Fuel Elements
Benjamin M. Ma, Glenn Murphy
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 536-546
Technical Paper | doi.org/10.13182/NSE64-A20997