ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Will Palisades be the “comeback kid”?
Mike Mlynarek believes in this expression: “In the end it will be OK; and if it’s not OK, it’s not the end.”
As the site vice president at Palisades nuclear power plant in Covert Township, Mich., Mlynarek is overseeing one of the most exciting projects in the United States nuclear power industry. If all goes according to plan, Holtec’s Palisades plant will be splitting atoms once again by the end of 2025 and become the first U.S. nuclear facility to restart after being slated for decommissioning.
Jump to:
The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations
José M. Aragonés, Carol Ahnert, and Nuria García-Herranz
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE07-A2709
Comparison and Extension of Dancoff Factors for Pebble-Bed Reactors
J. L. Kloosterman, A. M. Ougouag
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 16-29
Technical Paper | doi.org/10.13182/NSE07-A2710
Perturbation Theory Based on the Method of Cyclic Characteristics
M. Assawaroongruengchot, G. Marleau
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 30-50
Technical Paper | doi.org/10.13182/NSE07-A2711
Time Series Analysis of Monte Carlo Fission Sources - III: Coarse-Mesh Projection
Brian R. Nease, Taro Ueki
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 51-64
Technical Paper | doi.org/10.13182/NSE07-A2712
Gamma-Ray Production Cross Sections in Multiple Channels for Neutron-Induced Reaction on 48Ti for En = 1 to 200 MeV
D. Dashdorj, G. E. Mitchell, J. A. Becker, U. Agvaanluvsan, L. A. Bernstein, W. Younes, P. E. Garrett, M. B. Chadwick, M. Devlin, N. Fotiades, T. Kawano, R. O. Nelson
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 65-77
Technical Paper | doi.org/10.13182/NSE07-A2713
Calculation and Analysis of n + 180,182,183,184,186,natW Reactions in the En 250 MeV Energy Range
Yinlu Han, Yuyang Shi, Zhengjun Zhang
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 78-94
Technical Paper | doi.org/10.13182/NSE07-A2714
Vacuum Interface Analysis of a Windowless Spallation Target for Accelerator-Driven Systems
P. Michelato, E. Cavaliere, C. Pagani, E. Bari, A. Bonucci
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 95-109
Technical Paper | doi.org/10.13182/NSE07-A2715
Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P
Roberto Orsi
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 110-116
Computer Code Abstract | doi.org/10.13182/NSE07-A2716
Monte Carlo Variance Reduction for Energy Profile Calculation at the Electron Emission Due to Photon Radiation
Taro Ueki
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 119-131
Technical Paper | doi.org/10.13182/NSE07-A2717
Stopping Criteria of Inactive Cycle Monte Carlo Calculations
Hyung Jin Shim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 132-141
Technical Paper | doi.org/10.13182/NSE06-33
Secondary Neutron-Production Cross Sections from Heavy-Ion Interactions Between 230 and 600 MeV/Nucleon
L. Heilbronn, C. J. Zeitlin, Y. Iwata, T. Murakami, H. Iwase, T. Nakamura, T. Nunomiya, H. Sato, H. Yashima, R. M. Ronningen, K. Ieki
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 142-158
Technical Paper | doi.org/10.13182/NSE07-A2719
Calculation and Analysis for p + 58,60,61,62,64Ni Reactions Below 200 MeV
Chun-Tian Liang, Chong-Hai Cai
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 159-184
Technical Paper | doi.org/10.13182/NSE07-A2720
Definition of Breeding Gain for the Closed Fuel Cycle and Application to a Gas-Cooled Fast Reactor
W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, H. van Dam
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 185-199
Technical Paper | doi.org/10.13182/NSE07-A2721
Analyzing Nuclear Fuel Cycles from Isotopic Ratios of Waste Products Applicable to Measurement by Accelerator Mass Spectrometry
Scott M. Whitney, Steven Biegalski, Bruce Buchholz
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 200-209
Technical Paper | doi.org/10.13182/NSE07-A2722
Multigroup Coupled Neutron-Gamma Cross-Section Library for Deterministic and Monte Carlo Borehole-Logging Analysis
Ivo Kodeli, Daniel L. Aldama, Piet F. A. de Leege, David Legrady, J. Eduard Hoogenboom, Pat Cowan
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 210-224
Technical Note | doi.org/10.13182/NSE07-A2723
Escape and Transmission Probabilities in X-Y-Z Geometry
R. D. M. Garcia
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 225-235
Technical Note | doi.org/10.13182/NSE07-A2724
A New System to Fuel Loading and Control Rod Pattern Optimization in Boiling Water Reactors
Juan José Ortiz, Alejandro Castillo, José Luis Montes, Raúl Perusquía
Nuclear Science and Engineering | Volume 157 | Number 2 | October 2007 | Pages 236-244
Technical Note | doi.org/10.13182/NSE07-A2725
Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests
Kenji Yokoyama, Akira Shono, Makoto Ishikawa
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 249-263
Technical Paper | doi.org/10.13182/NSE06-109
Development of a Low-Enriched-Uranium Core for the MIT Reactor
T. H. Newton, Jr., M. S. Kazimi, E. E. Pilat
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 264-279
Technical Paper | doi.org/10.13182/NSE07-A2727
Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmarks in an NPP with VVER-440 Reactor
S. Kliem, S. Danilin, A. Hämäläinen, J. Hádek, A. Keresztúri, P. Siltanen
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 280-298
Technical Paper | doi.org/10.13182/NSE07-A2728
Application of Duality Principles to Reflector Homogenization
Jean Ragusa, Richard Sanchez, Simone Santandrea
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 299-315
Technical Paper | doi.org/10.13182/NSE07-A2729
Development of a Novel Dynamic Simulink Model of the GT-MHR Core
Mehdi Reisi Fard, Thomas E. Blue, Don W. Miller
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 316-330
Technical Paper | doi.org/10.13182/NSE07-A2730
A Thermal-Hydraulic Model for Catalytic Recombiners
Douglas W. Stamps
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 331-343
Technical Paper | doi.org/10.13182/NSE07-A2731
Computational Modeling of Coupled Thermomechanical and Neutron Transport Behavior in a Godiva-Like Nuclear Assembly
S. C. Wilson, S. R. Biegalski, R. L. Coats
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 344-353
Technical Paper | doi.org/10.13182/NSE06-28
Discrete Gamma Radiation in Interaction of 14.9-MeV Neutrons with Natural Copper
Hongyu Zhou, Fuguo Deng, Xiaoji Ding, Ming Hua, Qiaoge Zhu, Chao Wang, Qiang Zhao, Guoying Fan
Nuclear Science and Engineering | Volume 157 | Number 3 | November 2007 | Pages 354-367
Technical Note | doi.org/10.13182/NSE07-A2733
