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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.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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Art exhibit visits IIT
Nuclear power plant cooling towers are easily recognizable for their familiar hyperboloid shape. But an art exhibit running at the Illinois Institute of Technology in Chicago aims to give visitors a different perspective.
The Art of the Reactor, an exhibit by the National Museum of Nuclear Science and History and hosted by IIT’s Lewis College of Science and Letters, opened on November 4 and runs until Sunday, December 4 at Hermann Hall on the IIT campus.
International High-Level Radioactive Waste Management Conference
Thursday, November 17, 2022|10:00–11:45AM MST|Mesquite
Stylianos Chatzidakis (Purdue)
Brady D. Hanson
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Maximum Heat Load Configuration for NUHOMS® DSCs
Venkata Venigalla (ORANO TN), Hui Liu (ORANO TN)
Corrosion Resistant Coatings for Application on Spent Nuclear Fuel Canisters
Brendan Nation (Sandia ), Andrew Knight (Sandia ), Rebecca Schaller (Sandia ), Charles R. Bryan (Sandia )
Thermal Modeling of Hanford Lead Canister's Heated Canister Test
Sarah R. Suffield (PNNL), Christopher Grant (PNNL), Nicholas Klymyshyn (PNNL)
Decay Heat Measurements and Analysis for BWR Fuel with Shorter Cooling Time
Henrik Liljenfeldt (Noemi Analytics), Hatice Akkurt (EPRI), Robert Hall (EPRI), Fredrik Johansson (Swedish Nuclear Fuel and Waste Management Company (SKB)), Jesper Kierkegaard (Vattenfall Nuclear Fuel)
Pretest Analysis of Spent Nuclear Fuel in a Seismic Shake Table Test
Nicholas Klymyshyn (PNNL), Kevin Kadooka (PNNL), Taylor Mason (PNNL), Casey Spitz (PNNL), Pavlo Ivanusa (PNNL), James Fitzpatrick (PNNL)
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