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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
Jump to:
Characteristics of the Aerosol Produced from Burning Sodium and Plutonium
Harry J. Ettinger, William D. Moss, Harold Busey
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE67-A17237
Reactor Organic Coolants II: Electron-Irradiation Studies of Hydrogenated Terphenyls
M. Tomlinson, R. R. Tymko, Donna Wuschke
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 14-19
Technical Paper | doi.org/10.13182/NSE67-A17238
A Sol-Gel Thorium Oxide with Improved Dissolving Characteristics
E. R. Russell, M. L. Hyder, W. E. Prout, C. B. Goodlett
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 20-24
Technical Paper | doi.org/10.13182/NSE67-A17239
The Stability of Boiling-Water Reactors and Loops
L. G. Neal, S. M. Zivi
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 25-38
Technical Paper | doi.org/10.13182/NSE67-A17240
A Study of Fission-Neutron Spectra with High-Energy Activation Detectors—Part I. Detector Development and Excitation Measurements
James A. Grundl
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 39-53
Technical Paper | doi.org/10.13182/NSE67-A17241
Theory of Branching Processes of Neutrons in a Multiplying Medium
Keiichi Saito, Yukichi Taji
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 54-64
Technical Paper | doi.org/10.13182/NSE67-A17242
Investigation of Differential Energy and Angle for 137Cs Gamma Rays in Water and Air
Mary Alberg, Harold Beck, Keran O'Brien, James E. McLaughlin
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 65-74
Technical Paper | doi.org/10.13182/NSE67-A17243
Position-Dependent Neutron Spectra in a Multiplying Medium
R. J. Cerbone, R. E. Slovacek, E. R. Gaerttner
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 75-84
Technical Paper | doi.org/10.13182/NSE67-A17244
Anisotropic Scattering in Cell Problems
Pierre Benoist
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 85-94
Technical Paper | doi.org/10.13182/NSE67-A17245
Eigenfunction Analysis of Neutron-Wave Propagation in Moderating Media
M. J. Ohanian, R. S. Booth, R. B. Perez
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 95-103
Technical Paper | doi.org/10.13182/NSE67-A17246
The Delayed-Neutron Fraction—Neutron Lifetime Ratio in a TRIGA Reactor from Noise Analysis
Bruno Bärs
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 104-108
Technical Paper | doi.org/10.13182/NSE67-A17247
The Fast-Fission Effect in Lattices Consisting of Clustered Elements
Jacques Rognon
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 109-121
Technical Paper | doi.org/10.13182/NSE67-A17248
Thermal Disadvantage Factors and Fast Advantage Factors in Uranium-Thorium, Seed-Blanket Assemblies
S. S. Glickstein, P. H. Lehmann, L. L. Wheat, J. D. Korsmeyer, S. Milani, G. G. Smith, S. H. Weiss
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE67-A17249
Neutron Leakage Effects on the Fast Advantage Factor in a Seed-Blanket Assembly
S. S. Glickstein, J. W. Beck, L. L. Wheat, W. J. Hall
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 137-143
Technical Paper | doi.org/10.13182/NSE67-A17250
Molybdenum-99 Half-life Determination
M. N. Baldwin
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Page 144
Technical Note | doi.org/10.13182/NSE67-A17251
The Total Neutron Cross Section of Palladium from 0.005 to 10 eV
M. C. Teich, P. J. Schweitzer, C. A. Anderson, T. J. Thompson
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Page 145
Technical Note | doi.org/10.13182/NSE30-01-145TN
Iteration and Intermediate Resonance Absorption
Rubin Goldstein
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Page 146
Technical Note | doi.org/10.13182/NSE67-A17253
Effects of Moderator Temperature Gradients on Thermal-Neutron Flux
Michael D. Williams, Thomas E. Hicks
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 147-150
Technical Note | doi.org/10.13182/NSE67-A17254
Collision Probabilities for Finite Cylinders and Cuboids
I. Carlvik
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 150-151
Technical Note | doi.org/10.13182/NSE30-01-150TN
Convergence of the Source Iteration Technique in Solution of the Multigroup Neutron Transport or Diffusion Equations with External Source
N. Spinks
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 152-154
Technical Note | doi.org/10.13182/NSE67-A17256
Solvent Effects on Reaction Rates and Mechanisms
M. Lee Hyder
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Page 156
Book Review | doi.org/10.13182/NSE67-A17259
Optimal Shutdown Control of Nuclear Reactors
John J. Roberts
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 156-157
Book Review | doi.org/10.13182/NSE67-A17260
Thermal Stress and Low-Cycle Fatigue
S. H. Fistedis
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 157-158
Book Review | doi.org/10.13182/NSE67-A17261
Health Physics, Principles of Radiation Protection
Newton Underwood
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Page 158
Book Review | doi.org/10.13182/NSE67-A17262
Truncation of the Spherical Harmonic Expansion of the Transport Equation
Roger B. DeBar
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 159-165
Technical Paper | doi.org/10.13182/NSE67-A17326
A Perturbation Method Which Utilizes the Variational Principles Associated with the Neutron Diffusion Equation
Richard E. Turley
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 166-175
Technical Paper | doi.org/10.13182/NSE67-A17327
A Black-White Model for Including Epithermal Absorption in Calculations of Control-Rod Worth
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 176-181
Technical Paper | doi.org/10.13182/NSE67-A17328
An Analysis of the Mutual Interaction of Circumferential Control Plates
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 182-187
Technical Paper | doi.org/10.13182/NSE67-A17329
Reactor Noise in Heterogeneous Systems: I. Plate-Type Elements
M. M. R. Williams
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 188-198
Technical Paper | doi.org/10.13182/NSE67-A17330
Multiple Scattering in Slow-Neutron Double-Differential Measurements
E. L. Slaggie
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 199-212
Technical Paper | doi.org/10.13182/NSE67-A17331
Spatial Distributions in Water of Neutrons from a 2.85-MeV T(ρ,n)3He Source
R. W. Stooksberry, E. E. Carroll, Jr.
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 213-221
Technical Paper | doi.org/10.13182/NSE67-A17332
Atom Ratios and Effective Cross-Section Ratios in Highly Depleted Plutonium-Aluminum Alloy Fuel
W. A. Reardon, D. E. Christensen
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 222-232
Technical Paper | doi.org/10.13182/NSE67-A17333
Ionization by Fission Fragments Escaping from a Source Medium
Dong H. Nguyen, Lawrence M. Grossman
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 233-241
Technical Paper | doi.org/10.13182/NSE67-A17334
The Study of Thermal Neutrons in Shields Containing Ducts by Source-Separation Techniques
F. R. Channon, R. L. Seale
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 242-260
Technical Paper | doi.org/10.13182/NSE67-A17335
Experimental Studies on Gamma-Ray Dose Rates from a 60Co Cylindrical Source
Yutaka Furuta, Yoshihiko Kanemori
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 261-267
Technical Paper | doi.org/10.13182/NSE67-A17336
An Analytical Investigation of the Transient Response of the Volumetric Concentration in a Boiling Forced-Flow System
Novak Zuber, F. W. Staub
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 268-278
Technical Paper | doi.org/10.13182/NSE67-A17337
Experimental Investigation of the Transient Response of the Volumetric Concentration in a Boiling Forced-Flow System
F. W. Staub, N. Zuber, G. Bijwaard
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 279-295
Technical Paper | doi.org/10.13182/NSE67-A17338
Void Response to Flow and Power Oscillations in a Forced-Convection Boiling System with Axially Nonuniform Power Input
F. W. Staub, N. Zuber
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 296-303
Technical Paper | doi.org/10.13182/NSE67-A17339
Intermediate Resonance Absorption for Multi-Nuclide Systems
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Page 304
Technical Note | doi.org/10.13182/NSE67-A17340
An Improvement of the SN Calculation Method for Slab Geometry
J. J. Wagschal
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 305-307
Technical Note | doi.org/10.13182/NSE67-A17341
An Expression for the Remainder in the Spherical Harmonics Method
W. L. Hendry
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 307-308
Technical Note | doi.org/10.13182/NSE67-A17342
Neutron Emission Growth in Plutonium-Beryllium Sources
E. D. Jordan, W. H. Bedenbaugh, T. E. Carew
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 308-309
Technical Note | doi.org/10.13182/NSE67-A17343
Compatibility of Type-304 Stainless Steel with Sodium Paste Reactor Fuels
M. G. Chasanov
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 310-311
Technical Note | doi.org/10.13182/NSE67-A17344
Thermoelastic Dynamics of a Pulse Reactor
David Burgreen
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 317-327
Technical Paper | doi.org/10.13182/NSE67-A18395
The Use of Infinite Medium Spectra in Gamma-Ray Heating Calculations
T. E. Dudley, M. R. Mendelson, N. E. Holden
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 328-339
Technical Paper | doi.org/10.13182/NSE67-A18396
Neutron Fluxes in Concrete Ducts Arising from Incident Epicadmium Neutrons: Calculations and Experiments
R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 340-354
Technical Paper | doi.org/10.13182/NSE67-A18397
Neutron Total and Absorption Cross Sections of 238Pu
T. E. Young, F. B. Simpson, J. R. Berreth, M. S. Coops
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 355-361
Technical Paper | doi.org/10.13182/NSE67-A18398
Decay of Thermalized Neutron Fields in Graphite
C. H. Reed, C. N. Henry, A. A. Usner
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 362-373
Technical Paper | doi.org/10.13182/NSE67-A18399
Activation Measurement of the Doppler Effect for 238U Capture and 235U Fission in a Fast-Neutron Spectrum
G. R. Pflasterer, Jr., R. Sher
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 374-394
Technical Paper | doi.org/10.13182/NSE67-A18400
Reactor Analysis by Monte Carlo
H. Rief, H. Kschwendt
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 395-418
Technical Paper | doi.org/10.13182/NSE67-A18401
Application of the Natural Mode Approximation to Space-Time Reactor Problems
Larry R. Foulke, Elias P. Gyftopoulos
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 419-435
Technical Paper | doi.org/10.13182/NSE67-A18402
Sinusoidal Analysis of a Low-Power Nuclear Reactor by the Wentzel-Kramers-Brillouin Approach
Sevim Tan
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 436-447
Technical Paper | doi.org/10.13182/NSE67-A18403
Variational Functionals for Space-Time Neutronics
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 448-451
Technical Note | doi.org/10.13182/NSE67-A18404
A Perturbation Method for Analysis of Neutron-Source-Worth Experiments in Nuclear Reactors
A. Gandini
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 451-453
Technical Note | doi.org/10.13182/NSE67-A18405
Linear Analysis of Xenon Spatial Oscillations
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 453-455
Technical Note | doi.org/10.13182/NSE67-A18406
Neutron Diffusion Using a Modulated Source
G. A. Massel, M. R. Feix
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 455-458
Technical Note | doi.org/10.13182/NSE67-A18407
A Very Low-Temperature Nuclear Reactor
S. A. Dupree
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 458-461
Technical Note | doi.org/10.13182/NSE67-A18408
Total Gamma Energy Release Due to Thermal-Neutron Fission in 235U
N. E. Holden, M. R. Mendelson, T. E. Dudley
Nuclear Science and Engineering | Volume 30 | Number 3 | December 1967 | Pages 461-463
Technical Note | doi.org/10.13182/NSE67-A18409