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Meeting 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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Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
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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