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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!
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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|Panel|Sponsored by RPD
Monday, November 13, 2023|1:00–2:45PM EST|Lincoln West
Session Chair:
John Jackson (INL)
Alternate Chair:
Abdalla Abou-Jaoude (INL)
Session Organizer:
As MARVEL completes its 90% final design, this panel session will provide a deep dive into the intricacies of the reactor demonstration. This session will specifically revolve around the final system configuration, fuel performance evaluation, validation of thermal hydraulics using an experimental facility, instrumentation and controls, and the detailed construction for the reactor. The fuel performance presentation will delve into some of the characteristics of the MARVEL TRIGA-based fuel and its associated behavior under various operational scenarios, within the basis of current fuel qualification. The results from the PCAT experimental test facilities that is intended to validate the natural circulation behavior within MARVEL will be discussed. This will be followed by an overview of the MARVEL instrumentation and controls, including the core reactivity control systems. Lastly, the detailed planned construction and assembly blueprint for the reactor within the TREAT facility will be presented.
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