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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|Sponsored by FCWMD
Tuesday, November 19, 2024|3:15–5:00PM EST|Labrid A/B
Session Chair:
Leah Squires
Session Organizer:
Alternate Chair:
Christina Leggett
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Commercialization of High-Density High Assay Low Enriched Uranium Fuel Systems
3:15–3:35PM EST
Michael Catalan (PNNL), Matthew Pippin (Y-12 National Security Complex), Gunes Argon (BWXT Nuclear Fuels)
Paper
Phenomena Identification and Ranking Table for Spent Tri-Structural Isotropic (TRISO) Particles in Storage and Transportation
3:35–3:55PM EST
Kevin Kelly (EPRI), Thomas Dabrow (MPR Assoc.), Cecile Dame (MPR Assoc.), Dan Moneghan (EPRI)
Advanced Reactor Irradiated Graphite Lifecycle Analysis: From Source Term to Repository Performance
3:55–4:15PM EST
Liam S. Hines (MIT), Koroush Shirvan (MIT), Haruko Wainwight (MIT)
Nuclide Importance to Decay Heat in Advanced Reactors' Spent Fuel Transportation and Storage
4:15–4:35PM EST
Germina Procop (ORNL), Yves Robert (ORNL)
Presentation Slides (Visible to Attendees)
Preliminary Study for Recycling Heavy Metal from the Special Purpose Reactor Used Fuel in the Advanced Burner Reactor
4:35–4:55PM EST
Cihang Lu (Brookhaven), Arantxa Cuadra (Brookhaven)
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