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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
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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