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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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!
Latest Magazine Issues
Feb 2023
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
Latest News
University of Florida–led consortium to research nuclear forensics
A 16-university team of 31 scientists and engineers, under the title Consortium for Nuclear Forensics and led by the University of Florida, has been selected by the Department of Energy’s National Nuclear Security Administration (NNSA) to develop the next generation of new technologies and insights in nuclear forensics.
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Numerical Caseology by Lagrange Interpolation for the 1D Neutron Transport Equation in a Slab
B. D. Ganapol
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 1-13
Technical Paper | doi.org/10.1080/00295639.2022.2097494
Uncertainty Quantification of a Light Water Pulsed-Neutron Die-Away Experiment to Thermal Neutron Scattering Laws
Daniel Siefman, Mathieu Hursin, Catherine Percher, David Heinrichs
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 14-24
Technical Paper | doi.org/10.1080/00295639.2022.2103344
Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission of 244Cm
H. Naik, R. J. Singh, W. Jang
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 25-44
Technical Paper | doi.org/10.1080/00295639.2022.2103345
An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment
Aaron J. Reynolds, Todd S. Palmer
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 45-73
Technical Paper | doi.org/10.1080/00295639.2022.2097565
Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under Uniform and Nonuniform High-Flux Heat Inputs
Dong Yang, Lin Chen, Yongchang Feng, Haisheng Chen
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 74-91
Technical Paper | doi.org/10.1080/00295639.2022.2102391
Development of an Activity Transport Model and In Situ Measurements on Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan Nuclear Power Plant
Yu-Hung Shih, Mei-Ya Wang, Tsuey-Lin Tsai, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 92-103
Technical Paper | doi.org/10.1080/00295639.2022.2102392
Infiltration and Evaporation in Multiplying Porous Media and Associated Criticality Phenomena
M. M. R. Williams
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 104-131
Technical Paper | doi.org/10.1080/00295639.2022.2103336
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study
M. Chandra Kumar, A. Jasmin Sudha, V. Subramanian, S. Athmalingam, B. Venkatraman
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 132-143
Technical Paper | doi.org/10.1080/00295639.2022.2103338
Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations
Edward W. Larsen
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 145-163
Technical Paper | doi.org/10.1080/00295639.2022.2058847
Toward a More Realistic Analysis of Neutron Clustering
Thomas M. Sutton
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 164-175
Technical Paper | doi.org/10.1080/00295639.2022.2065872
Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation
Tomohiro Endo, Fuga Nishioka, Akio Yamamoto, Kenichi Watanabe, Cheol Ho Pyeon
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 176-188
Technical Paper | doi.org/10.1080/00295639.2022.2049992
A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy
Anil K. Prinja, Patrick F. O’Rourke
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 189-211
Technical Paper | doi.org/10.1080/00295639.2022.2087830
A Limited-Memory Framework for Conditional Point Sampling for Radiation Transport in 1D Stochastic Media
Emily H. Vu, Aaron J. Olson
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 212-232
Technical Paper | doi.org/10.1080/00295639.2022.2116378
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators
Patrick Behne, Jan Vermaak, Jean Ragusa
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 233-261
Technical Paper | doi.org/10.1080/00295639.2022.2112901
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems
Nickolas J. Adamowicz, Annalisa Manera, Edward W. Larsen
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 262-278
Technical Paper | doi.org/10.1080/00295639.2022.2112900
Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo
Miriam A. Kreher, Samuel Shaner, Benoit Forget, Kord Smith
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 279-290
Technical Paper | doi.org/10.1080/00295639.2022.2067739
The Legendre Polynomial Axial Expansion Method
Nicholas F. Herring, Benjamin S. Collins, Thomas J. Downar, Aaron M. Graham
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 291-307
Technical Paper | doi.org/10.1080/00295639.2022.2082231
A Multigroup Homogeneous Flux Reconstruction Method Based on the ANOVA-HDMR Decomposition
Pavel M. Bokov, Danniell Botes, Rian H. Prinsloo, Djordje I. Tomašević
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 308-332
Technical Paper | doi.org/10.1080/00295639.2022.2108654
Spatially Dependent Resonance Self-Shielding in CASMO5
Rodolfo M. Ferrer, Joshua M. Hykes
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 333-350
Technical Paper | doi.org/10.1080/00295639.2022.2053491
