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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
CNL investigates alloy with potential reactor applications
A research team led by Canadian Nuclear Laboratories is studying a type of high-entropy alloy (HEA) that seems to withstand a cascade-involved irradiation environment at elevated temperatures better than stainless steel exposed to similar conditions. In a paper published in the Journal of Nuclear Materials, the researchers describe an HEA made of chromium, iron, manganese, and nickel (CrFeMnNi) that has the potential to improve the safety and functionality of nuclear reactors, as well as of spacecraft.
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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