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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
Fusion Science and Technology
Belgium mulls life extension for more reactors
The Belgian government is exploring the idea of extending the operational life of its three oldest reactors by two years, a variety of news outlets are reporting.
Those reactors—Units 1 and 2 at the Doel facility and Unit 1 at Tihange, sporting a combined capacity of 1,852 MWe—were slated to be permanently shuttered in 2025 in keeping with the country’s nuclear phase-out policy.
Technical Session|Used Fuel Storage, Transportation, and Re-Use
Tuesday, October 11, 2022|3:30–5:10PM EDT|Adagio/Allegro
Brady Hanson (PNNL)
Anzhelika Khaperskaia (IAEA)
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Spent Fuel Burnup Measurement System: Evolution of SICOM-NG-FA for Republic of Korea Nuclear Power Plants
Roberto Rodríguez (ENUSA ), Ivan Sánchez (ENUSA ), Angel Ramos (ENUSA ), Miriam Vázquez (ENUSA ), Alfonso Lain (TECNATOM), Hyeong Kim (KEPCO-Nuclear Fuel Co.), Manseok Do (KEPCO-Nuclear Fuel Co.)
The Development of a PWR Spent Fuel Decay Heat Uncertainty Methodology Applicable to MOX and UOX Fuel
Matthias Vanderhaegen (Tractebel Engineering), Quivy Bernard (Tractebel Engineering), Slosse Nicolas (Tractebel Engineering), Meert Arnaud (ENGIE Electrabel), Stichelbout Jonas (ENGIE Electrabel)
The Licensing of a PWR Spent Fuel Decay Heat Uncertainty Methodology Applicable to MOX and UOX Fuel Developed by Tractebel
N.A. Hollasky (Bel V), M. Vincke (Bel V)
Transport of Irradiated Nuclear Fuel Between Reactor Sites for Further Use
Rickard Land (Forsmark), Sofia Nilsson (Forsmark), Jesper Kierkegaard (Vattenfall Nuclear Fuel)
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