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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
Carolyn McGraw, Germina Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 436-445
Technical Paper | Fission Reactors / Radiation Transport and Protection | doi.org/10.13182/NT13-A19431
Articles are hosted by Taylor and Francis Online.
New pressurized water reactor (PWR) cross-section libraries were generated for use with the ORIGEN-ARP depletion sequence in the SCALE nuclear analysis code system. These libraries are based on ENDF/B-VII.0 nuclear data and were generated using the two-dimensional depletion sequence, TRITON/NEWT, in SCALE 6.1. The libraries contain multiple burnup-dependent cross sections for seven PWR fuel designs, with enrichments ranging from 1.5 to 6 wt% 235U and burnups from 0 to 90 GW(d)/tonne U. The computational methodology and studies performed to establish an optimal depletion model for cross-section library generation are discussed in this paper. Verification against detailed TRITON simulations for the considered assembly designs showed that depletion calculations performed in ORIGEN-ARP with the pregenerated libraries provide results similar to those obtained with direct TRITON depletion while greatly reducing the computation time. Validation of the libraries, carried out using radiochemical assay measurements and decay heat measurements for PWR spent fuel, showed good agreement between calculated and experimental data.
