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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.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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
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A fateful day for nuclear waste policy: January 31, 1998
Next week will mark 25 years since January 31, 1998, a familiar date to most in the nuclear community, and revisited in today’s #ThrowbackThursday post with an article from the March 1998 issue of Nuclear News. “Those in the nuclear power industry are aware of the significance of the date January 31, 1998. ln the Nuclear Waste Policy Act of 1982, that date was set as the deadline for the U.S. government—more specifically, the Department of Energy—to begin taking possession of and responsibility for spent nuclear fuel from nuclear power plants nationwide” (NN, March 1998, p. 59).
Technical Session|Sponsored by Mathematics & Computation
Saturday, April 16, 2022|8:00–9:30AM CDT|Honors Room
Sponsored by ANS Mathematics & Computation Division
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Machine Learning Classification for Safety Analysis of Nuclear Research Reactor Experiments
Roberto Fairhurst Agosta (Univ. Illinois, Urbana-Champaign), Tomasz Kozlowski (Univ. Illinois, Urbana-Champaign)
Evaluation of HYPRE Preconditioners for Use in Solving CMFD-Accelerated Neutron Diffusion Problems
Thomas Jayasankar (Univ. Michigan), Qicang Shen (Univ. Michigan), Brendan M. Kochunas (Univ. Michigan)
Statistical Surrogate for High-Fidelity Turbulent Channel Flow
Molly Ross (Kansas State), Hitesh Bindra (Kansas State)
Modelling of Hydrogen Adsorption and Diffusion in Graphite Using a Genetic Algorithm
Lorenzo Vergari (Univ. California, Berkeley), Amit Bhat (Univ. California, Berkeley), Raluca O. Scarlat (Univ. California, Berkeley)
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