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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
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Apr 2024
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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
Technical Session|Used Fuel Storage, Transportation, and Re-Use
Tuesday, October 11, 2022|3:30–5:10PM EDT|Adagio/Allegro
Session Chair:
Brady Hanson (PNNL)
Alternate Chair:
Anzhelika Khaperskaia (IAEA)
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Spent Fuel Burnup Measurement System: Evolution of SICOM-NG-FA for Republic of Korea Nuclear Power Plants
3:30–3:55PM EDT
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.)
Paper
The Development of a PWR Spent Fuel Decay Heat Uncertainty Methodology Applicable to MOX and UOX Fuel
3:55–4:20PM EDT
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
4:20–4:45PM EDT
N.A. Hollasky (Bel V), M. Vincke (Bel V)
Transport of Irradiated Nuclear Fuel Between Reactor Sites for Further Use
4:45–5:10PM EDT
Rickard Land (Forsmark), Sofia Nilsson (Forsmark), Jesper Kierkegaard (Vattenfall Nuclear Fuel)
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