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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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Measurement of the Neutron Fission and Capture Cross Sections for 233U in the Energy Region 0.4 to 2000 eV
L. W. Weston, R. Gwin, and G. deSaussure, R. R. Fullwood and R. W. Hockenbury
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE68-A19361
Absolute Fission Rate Measurements with Solid-State Track Recorders
Raymond Gold and Roland J. Armani, James H. Roberts
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 13-32
Technical Paper | doi.org/10.13182/NSE68-A19362
Neutron-Wave Propagation Through a Crystalline Moderator-II: Graphite
Feroz Ahmed, P. S. Grover and L. S. Kothari
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 33-38
Technical Paper | doi.org/10.13182/NSE68-A19363
Effective Source Strength for Arbitrarily Anisotropic Neutron Scattering in Infinite Medium
E. İnönü and A. İ. Usseli
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 39-44
Technical Paper | doi.org/10.13182/NSE68-A19364
A Variational Multichannel Space-Time Synthesis Method for Nonseparable Reactor Transients
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 45-56
Technical Paper | doi.org/10.13182/NSE68-A19365
Positivity Theorems for the Discrete Form of the Multigroup Diffusion Equations
Reimar Froehlich
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 57-66
Technical Paper | doi.org/10.13182/NSE68-A19366
Numerical Comparison of Diffusion-Like Transport Approximations for Very Fast Neutrons
L. B. Freeman and H. W. Ryals
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 67-75
Technical Paper | doi.org/10.13182/NSE68-A19367
A New Derivation of Discrete Ordinate Approximations
Stanley Kaplan
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 76-82
Technical Paper | doi.org/10.13182/NSE68-A19368
MSn, A New Approach to Neutron Transport Analysis
Shoichiro Nakamura
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 83-86
Technical Note | doi.org/10.13182/NSE68-A19369
Geometric Buckling of Polygonal Reactors
Raymond L. Murray, Thomas J. Hirons, Raymond J. Reith, and Owen J. Smith
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Pages 86-87
Technical Note | doi.org/10.13182/NSE68-A19370
The Determination of the Eigenvalues and Eigenfunctions Corresponding to Azimuthal Harmonics of a Reactor Having RZ Symmetry
F. D. Judge
Nuclear Science and Engineering | Volume 34 | Number 1 | October 1968 | Page 87
Technical Note | doi.org/10.13182/NSE68-A19371
On the Calculation of Neutron Inelastic Scattering Cross Sections
Mark Goldsmith
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 93-97
Technical Paper | doi.org/10.13182/NSE68-A19534
An Experimental Investigation of Spatial Effects on the Neutron Fluctuation Spectra of a Large Reactor
A. R. Buhl, S. H. Hanauer, N. P. Baumann
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 98-103
Technical Paper | doi.org/10.13182/NSE68-A19535
Thermal-Neutron Flux Generation by High-Energy Protons
W. A. Coleman, R. G. Alsmiller, Jr.
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 104-113
Technical Paper | doi.org/10.13182/NSE68-A19536
Experimental Evaluation of Minima in the Total Neutron Cross Sections of Several Shielding Materials
E. A. Straker
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 114-121
Technical Paper | doi.org/10.13182/NSE68-A19537
Space-Angle Energy-Time-Dependent Neutron Transport in a Homogeneous Slab by the jN Method
T. Asaoka
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 122-133
Technical Paper | doi.org/10.13182/NSE68-A19538
Solution to the Neutron Transport Equation for an Infinite Cylinder by Fourier Series
W. L. Hendry
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 134-147
Technical Paper | doi.org/10.13182/NSE68-A19539
Transient Temperature Distribution in a Reactor Channel with Cylindrical Fuel Rods and Compressible Coolant
Heinz Vollmer
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 148-157
Technical Paper | doi.org/10.13182/NSE68-A19540
Numerical Studies of Combined Space-Time Synthesis
J. B. Yasinsky
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 158-168
Technical Paper | doi.org/10.13182/NSE68-A19541
Spectrum of Gamma Rays Emitted by a Stainless Steel Clad, Pool-Type Reactor (BSR-II)
G. T. Chapman, W. R. Burrus
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 169-180
Technical Paper | doi.org/10.13182/NSE68-A19542
The Construction of Statistical Neutron Resonances
M. W. Dyos
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 181-188
Technical Paper | doi.org/10.13182/NSE68-A19543
Cross Flow and Mixing of Water Between Semiopen Channels
G. Hetsroni, J. Leon,, M. Hakim
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 189-193
Technical Paper | doi.org/10.13182/NSE68-A19544
Additional Conditions to the Neutron Multiplication Method of Reactivity Determination
S. Chwaszczewski
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 194-195
Technical Note | doi.org/10.13182/NSE68-A19545
Revised Value for the Thermal-Neutron Capture Cross Section of Deuterium
Janet S. Merritt, J. G. V. Taylor, A. W. Boyd
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 195-196
Technical Note | doi.org/10.13182/NSE68-A19546
On the Expansion of Experimental Functions in Series of Descending Exponentials of Real Argument
Fr. J. Servais
Nuclear Science and Engineering | Volume 34 | Number 2 | November 1968 | Pages 196-197
Technical Note | doi.org/10.13182/NSE68-A19547
A Study of the Release of Radioactive Metallic Isotopes from High-Temperature Gas-Cooled Reactors
J. Appel and B. Roos
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 201-213
Technical Paper | doi.org/10.13182/NSE68-A21086
Removal of Water and Carbon Dioxide from Helium Coolants by Molecular Sieves
Charles D. Scott
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 214-223
Technical Paper | doi.org/10.13182/NSE68-A21087
Inelastic Scattering of Thermal Neutrons in Graphite
F. Carvalho
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 224-236
Technical Paper | doi.org/10.13182/NSE68-A21088
Criticality Measurements on Nearly Homogeneous Enriched Uranium-Graphite Systems
James P. Phelps and Eugene V. Weinstock
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 237-250
Technical Paper | doi.org/10.13182/NSE68-A21089
Analysis of Brookhaven 235U-Graphite Critical Experiments
Bal Raj Sehgal
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 251-262
Technical Paper | doi.org/10.13182/NSE68-A21090
Analysis of a Set of Critical Homogeneous U-H2O Spheres
Alan Staub, D. R. Harris, and Mark Goldsmith
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 263-274
Technical Paper | doi.org/10.13182/NSE68-A21091
A Pulsed-Neutron Investigation of the Effect of Temperature on the Decay of a Thermal-Neutron Population in H2O Ice
Ernest G. Silver
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 275-284
Technical Paper | doi.org/10.13182/NSE68-A21092
Streaming Effects and Collision Probabilities in Lattices
P. Benoist
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 285-307
Technical Paper | doi.org/10.13182/NSE68-3
The Calculation of Neutron Flux Ratios in Critical Systems by the Indirect Variational Method
G. C. Pomraning
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 308-312
Technical Paper | doi.org/10.13182/NSE68-A21094
An Analysis of Methods for Calculating Spatially Dependent Neutron Slowing Down Distributions
Harvey J. Amster
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 313-327
Technical Paper | doi.org/10.13182/NSE68-A21095
Linear Energy Transformation for Gamma-Ray Monte Carlo Calculations
A. B. Chilton
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 328-329
Technical Note | doi.org/10.13182/NSE68-A21096
Evaluation of Neutron Absorption Rates by Activation Measurements of Spectral Indexes
F. Pistella
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 329-331
Technical Note | doi.org/10.13182/NSE68-A21097
Self-Shielding Factors for Scattering Dominant Neutron Resonances
W. H. Roach
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 331-332
Technical Note | doi.org/10.13182/NSE68-A21098
Sensitivity of Neutron Transport in Oxygen to Various Cross-Section Sets
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 332-336
Technical Note | doi.org/10.13182/NSE68-A21099
Applications of a Macroscopic Formulation of Transport Theory
W. Pfeiffer and J. L. Shapiro
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 336-339
Technical Note | doi.org/10.13182/NSE68-A21100
Overlapping Group Methods with Discontinuous Trial Functions
Martin Becker
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 339-341
Technical Note | doi.org/10.13182/NSE68-A21101
On the Use of Different Radial Trial Functions in Different Axial Zones of a Neutron Flux Synthesis Computation
E. L. Wachspress
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 342-343
Technical Note | doi.org/10.13182/NSE68-A21102
Asymmetric Discontinuities in Synthesis Techniques for Initial-Value Problems
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 343-344
Technical Note | doi.org/10.13182/NSE68-A21103
Verification of a Xenon Spatial Stability Criterion
Richard J. Hooper, Roger A. Rydin, and Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 34 | Number 3 | December 1968 | Pages 344-346
Technical Note | doi.org/10.13182/NSE68-A21104
