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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
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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
