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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
Charles S. Olsen, Steven M. Jensen, Eric R. Carlson, Beverly A. Cook
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 57-94
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27639
Articles are hosted by Taylor and Francis Online.
Core debris samples obtained from different regions of the Three Mile Island Unit 2 (TMI-2) core were examined to characterize the interaction among core components and the coolant, to determine the peak temperatures at which the interactions occurred, and to evaluate core melt progression in TMI-2. Estimates of peak temperatures were needed from these samples because of the strong influence that temperature has on core damage progression and fission product behavior. The peak temperatures can be bounded by comparing the observed microstructure and compositions with established phase diagrams. The microstructures were determined by optical metallography and scanning electron microscopy, and compositions were determined by energy and wavelength dispersive X-ray spectroscopy and scanning Auger spectroscopy. The material interactions among the core components are very complex and involve not only the interaction between the Zircaloy cladding and the UO2 fuel, but interactions with control rod materials (Ag-In-Cd) and Inconel spacer grids as well. Phase diagrams do not exist for some of the complex combinations of materials, and the models may have to be simplified and concentrated on the more significant interactions that involve material transport. The present models for core melt progression need to incorporate these more complex interactions in order to more closely predict the behavior of a core during a severe accident such as temperatures for material relocation.