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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
Fusion Science and Technology
Granholm visits Clinch River Site to show support for SMRs
Energy secretary Jennifer Granholm visited the Clinch River Nuclear Site in Oak Ridge, Tenn., on December 5 to highlight the Biden administration’s support for the Tennessee Valley Authority’s advanced nuclear technology program.
Granholm indicated that the administration is willing to provide funding for the nation’s first commercial small modular reactor at the site. “Excited to see a shovel in the ground, hopefully in a few more years,” she said. “TVA is leading on small modular reactors with this site. Everybody’s looking to TVA to make sure that this can actually happen.”
Tuesday, October 5, 2021|1:20–3:00PM EDT
James Warsa (LANL)
Dmitriy Y. Anistratov (NC State Univ.)
Charles Goodman (NC State Univ.)
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Fourier Analysis of Coarse Mesh Finite Difference and Linear Diffusion Acceleration for Spatially Heterogeneous Systems
Zackary Dodson (Univ. of Michigan), Brendan Kochunas (Univ. of Michigan), Edward Larsen (Univ. of Michigan)
Arbitrary-Level Hierarchical CMFD Acceleration for Diffusion Eigenvalue Problems
Michael W. Hackemack (Naval Nuclear Laboratory)
Convergence Acceleration Aspects in the Solution of PN Neutron Transport Eigenvalue Problem
N. Abrate (Politecnico di Torino), B. D. Ganapol (Univ. of Arizona), S. Dulla (Politecnico di Torino), P. Saracco (INFN), P. Ravetto (Politecnico di Torino), A. Zoia (CEA)
Attachment — version 2
Investigating Mixed FEM SPn as a Synthetic Acceleration for the DFE Transport Equation
Atyab A. Calloo (Polytechnique Montreal), Alain Hébert (Polytechnique Montreal)
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