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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
Thursday, May 19, 2022|10:15AM–12:00PM EDT|Fountainview
Session Chair:
Rodolfo M. Ferrer (Studsvik Scandpower)
Alternate Chair:
Benjamin R. Betzler (ORNL)
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Study of Neutronic Phenomenology of Heterogeneous Moderator Voiding in a Partially MOX-Loaded PWR
Sébastien De Mattei (CEA), Géraud Prulhière (CEA), Guillaume Martin (CEA), Jean-François Vidal (CEA)
Paper
KONVOI Core Analysis with CASMO5 and SIMULATE5
Emiliya L. Georgieva (Studsvik Scandpower), Marcus Seidl (PreussenElektra), Gerd Anton (Studsvik Scandpower)
Comparative Neutronic Analysis of an Accident Tolerant Fuel Loaded PWR by STREAM/RAST-K
Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)
Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels
B. R. Betzler (ORNL), J. Bae (ORNL), D. Chandler (ORNL), G. Ilas (ORNL), E. E. Davidson (ORNL)
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