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Division Spotlight
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.
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
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November 2024
Latest News
Terrestrial Energy looks at EnergySolutions-owned sites for IMSR plants
Advanced reactor developer Terrestrial Energy and Utah-based waste management company EnergySolutions announced they have signed a memorandum of understanding to collaborate on the siting and deployment of Terrestrial Energy’s integral molten salt reactor plants at EnergySolutions-owned sites.
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Neutronic Feasibility Assessment of Liquid Salt-Cooled Pebble Bed Reactors
Massimiliano Fratoni, Ehud Greenspan
Nuclear Science and Engineering | Volume 168 | Number 1 | May 2011 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE10-38
Detailed Design of 242mAm Breeding in Pressurized Water Reactors
Leonid Golyand, Yigal Ronen, Eugene Shwageraus
Nuclear Science and Engineering | Volume 168 | Number 1 | May 2011 | Pages 23-36
Technical Paper | doi.org/10.13182/NSE09-43
Newton's Method for the Computation of k-Eigenvalues in SN Transport Applications
Daniel F. Gill, Yousry Y. Azmy, James S. Warsa, Jeffery D. Densmore
Nuclear Science and Engineering | Volume 168 | Number 1 | May 2011 | Pages 37-58
Technical Paper | doi.org/10.13182/NSE10-01
An Analysis of Reflector Homogenization Techniques for Full Core Diffusion Calculations
Charlotte Sandrin, Richard Sanchez, Florence Dolci
Nuclear Science and Engineering | Volume 168 | Number 1 | May 2011 | Pages 59-72
Technical Paper | doi.org/10.13182/NSE10-44
Improved Derivation of Multigroup Effective Cross Section for Heterogeneous System by Equivalence Theory
Akio Yamamoto, Tomohiro Endo, Hiroki Koike
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 75-92
Technical Paper | doi.org/10.13182/NSE10-50
Application of Time-Dependent Neutron Transport Theory to High-Temperature Reactors of Pebble Bed Type
Bismark Tyobeka, Andreas Pautz, Kostadin Ivanov
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 93-114
Technical Paper | doi.org/10.13182/NSE10-60
On the Accuracy of a Common Monte Carlo Surface Flux Grazing Approximation
Jeffrey A. Favorite, Ashley D. Thomas, Thomas E. Booth
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 115-127
Technical Paper | doi.org/10.13182/NSE09-72
Perspectives on Advanced Simulation for Nuclear Reactor Safety Applications
J. Kelly, M. Corradini, R. Budnitz, M. Pilch
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 128-137
Technical Paper | doi.org/10.13182/NSE10-85
Calculation of the Void Fraction and Void Coefficient in an Aqueous Homogeneous Reactor
M. M. R. Williams
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 138-150
Technical Paper | doi.org/10.13182/NSE11-45
Calculation and Analysis of Neutron-Induced Reactions on 59Co up to 200 MeV
Yue Zhang, Yinlu Han, Hairui Guo, Qingbiao Shen
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 151-163
Technical Paper | doi.org/10.13182/NSE09-001
Measuring (n, f) Cross Sections of Short-Lived States
J. I. Katz
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 164-171
Technical Paper | doi.org/10.13182/NSE10-19
Tritium Battery with Solid Dielectric
A. Kavetskiy, G. Yakubova, S. M. Yousaf, K. Bower
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 172-179
Technical Paper | doi.org/10.13182/NSE10-49
Interpolation of Temperature-Dependent Nuclide Data in MCNP
J. V. Donnelly
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 180-184
Technical Note | doi.org/10.13182/NSE10-76
Evaluation of Dynamic Pressures from Steam Explosions Applied to Advanced Light Water Reactors
Michael L. Corradini, James P. Blanchard, Carl J. Martin
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 185-196
Technical Paper | doi.org/10.13182/NSE10-24
Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling Methods
Rong Kong, Jerome Spanier
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 197-225
Technical Paper | Geometric Convergence of Adaptive Monte Carlo Algorithms for Radiative Transport Problems Based on Importance Sampling Methods | doi.org/10.13182/NSE10-29
Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo
Brian C. Kiedrowski, Forrest B. Brown, Paul P. H. Wilson
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 226-241
Technical Paper | doi.org/10.13182/NSE10-22
Using Core Symmetry in Monte Carlo Dominance Ratio Calculations
Sergey S. Gorodkov
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 242-247
Technical Paper | doi.org/10.13182/NSE10-37
Stochastic Invariant Imbedding Theory for a Distributed Internal Source
S. B. Degweker, Imre Pázsit
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 248-264
Technical Paper | doi.org/10.13182/NSE10-08
Deterministic and Stochastic Evaluation of Criticality Excursion Power Bursts
Scott D. Ramsey, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 265-277
Technical Paper | doi.org/10.13182/NSE10-11
Simplified Simulation of Fast Neutron Scattering for an Explosives Detection Application
A. L. Lehnert, K. J. Kearfott
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 278-286
Technical Paper | doi.org/10.13182/NSE10-13
An Experimental Study on Radon Adsorption Ability and Microstructure of Activated Carbon
Qingbo Wang, Jingyuan Qu, Wenkai Zhu, Baichang Zhou, Jinxing Cheng
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 287-292
Technical Note | doi.org/10.13182/NSE10-65
