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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
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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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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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Markovian Reliability Analysis Under Uncertainty with an Application on the Shutdown System of the Clinch River Breeder Reactor
Ioannis A. Papazoglou, Elias P. Gyftopoulos
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE80-A18703
Heat Transfer and Pressure Drop in Sodium Boiling in Tubes
Yu. A. Zeigarnick, V. D. Litvinov
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 19-28
Technical Paper | doi.org/10.13182/NSE80-A18704
Radiation Damage by High-Energy Neutrons
William Primak
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 29-34
Technical Paper | doi.org/10.13182/NSE80-A18705
Neutron Spectra from Monoenergetic Source Neutrons After Multiple Reflection Between Plane-Parallel Concrete Interfaces
William K. Hagan, G. L. Simmons
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 35-41
Technical Paper | doi.org/10.13182/NSE80-A18706
Fission Product Yields for Thermal-Neutron Fission of Plutonium-239
J. K. Dickens, J. W. McConnell
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 42-55
Technical Paper | doi.org/10.13182/NSE80-A18707
Some Results of Transfer Matrix Calculations for Thermal Neutrons
Seong-Youn Kim, Raphael Aronson
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 56-65
Technical Paper | doi.org/10.13182/NSE80-A18708
Variance Versus Efficiency in Transport Monte Carlo
Iván Lux
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 66-75
Technical Paper | doi.org/10.13182/NSE80-A18709
Convergence Rates of Spatial Difference Equations for the Discrete-Ordinates Neutron Transport Equations in Slab Geometry
Edward W. Larsen, Warren F. Miller, Jr.
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 76-83
Technical Paper | doi.org/10.13182/NSE80-3
Probability Level of Readiness in Supervised Protective Systems for Nuclear Reactors
J. M. Kontoleon
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 84-86
Technical Note | doi.org/10.13182/NSE80-A18711
Comparison of One- and Two-Dimensional Cross-Section Sensitivity Calculations for a Fusion Reactor Shielding Experiment
Y. Seki, R. T. Santoro, E. M. Oblow, J. L. Lucius
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 87-93
Technical Note | doi.org/10.13182/NSE80-A18712
Optimized Smoothing in Neutron Spectrum Unfolding by the FERDOR Method
R. H. Johnson, B. W. Wehring, J. J. Dorning
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 93-97
Technical Note | doi.org/10.13182/NSE80-A18713
Photon Point Source Buildup Factors for Air, Water, and Iron
A. B. Chilton, C. M. Eisenhauer, G. L. Simmons
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 97-107
Technical Note | doi.org/10.13182/NSE80-A18714
Monte Carlo Treatment for Neutral Particle Transport Problems in a Toroidal Plasma
S. Inoue, Y. Taji, Y. Nakahara, T. Suzuki
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 119-124
Technical Paper | doi.org/10.13182/NSE80-A18692
A Rigorous Treatment of Transverse Buckling Effects in Two-Dimensional Neutron Transport Computations
R. N. Blomquist, E. E. Lewis
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 125-139
Technical Paper | doi.org/10.13182/NSE80-A18693
Time-Optimal Control of Spatial Xenon Oscillations to a Generalized Target
Earl J. Schulz, John C. Lee
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 140-152
Technical Paper | doi.org/10.13182/NSE80-A18694
Experimental Determination of Photofission Neutron Multiplicities for 235U, 236U, 238U, and 232Th Using Monoenergetic Photons
J. T. Caldwell, E. J. Dowdy, R. A. Alvarez, B. L. Berman, P. Meyer
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 153-163
Technical Paper | doi.org/10.13182/NSE80-A18695
Resonance Absorption in High-Temperature Gas-Cooled Reactor Fuel with Double Heterogeneity
Keiichiro Tsuchihashi, Yukio Ishiguro, Kunio Kaneko
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 164-173
Technical Paper | doi.org/10.13182/NSE80-A18696
100,101,102,104,Ru(n, γ) and 103Rh(n, γ) Cross Sections Above 2.6 keV
R. L. Macklin, J. Halperin
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 174-185
Technical Paper | doi.org/10.13182/NSE80-A18697
Scattering of MeV Neutrons from Elemental Iron
A. Smith, P. Guenther
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 186-195
Technical Paper | doi.org/10.13182/NSE80-A18698
Numerical Simulation of Boiling Water Reactor Vent-Clearing Hydrodynamics
B. D. Nichols, C. W. Hirt
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 196-209
Technical Paper | doi.org/10.13182/NSE80-A18699
Time-Dependent Generalized Perturbation Theory for Coupled Neutron-Nuclide Problems
E. Greenspan, M. L. Williams, J. H. Marable
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 210-218
Technical Note | doi.org/10.13182/NSE80-A18700
A Numerical Study of Weakly Compressible Rotating Flows in a Gas Centrifuge
Iwao Harada
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 225-241
Technical Paper | doi.org/10.13182/NSE80-A19848
The Effects of Sodium Entrainment and Heat Transfer with Two-Phase UO2 During a Hypothetical Core Disruptive Accident
Michael L. Corradini, Warren M. Rohsenow, Neil E. Todreas
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 242-258
Technical Paper | doi.org/10.13182/NSE80-A19849
Neutron and Gamma-Ray Penetrations in Thick Iron
Yoshiaki Oka, Shigehiro An, Shigeru Kasai, Shun-ichi Miyasaka, Kinji Koyama
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 259-273
Technical Paper | doi.org/10.13182/NSE80-A19850
Homogenized Diffusion Approximations to the Neutron Transport Equation
Edward W. Larsen, R. P. Hughes
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 274-285
Technical Paper | doi.org/10.13182/NSE80-A19851
Parameter Estimation of Liquid-Metal Fast Breeder Reactor Simulation Experiments Using Univariate Autoregressive Integrated Moving Average Modeling
M. I. Pekarsky, C. C. Meek, R. C. Doerner
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 286-289
Technical Note | doi.org/10.13182/NSE80-A19852
Comments on Higher Order Generalized Perturbation Theory
A. Gandini
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 289-294
Technical Note | doi.org/10.13182/NSE80-A19853
Multidimensional Space-Time Kinetics of a Heavy-Water-Moderated Nuclear Reactor
W. G. Winn, N. P. Baumann, C. E. Jewell
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 294-300
Technical Note | doi.org/10.13182/NSE80-A19854