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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
Kazuo Takino, Kazuteru Sugino, Kenji Yokoyama (JAEA), Tomoyuki Jin (NESI Inc.), Shigeo Ohki (JAEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1214-1220
Since next-generation fast reactors aim to achieve a higher core discharge burn-up than that of the conventional ones, nuclear design methods need to refine. In this study, we investigated the effect that the analysis conditions exhibit on the accuracy of estimations of the burn-up nuclear characteristics of next-generation fast reactors. Suitable analysis schemes and conditions that maximize the estimation accuracy, while maintaining a low computational cost, were investigated in this study.
We performed core burn-up survey calculations under several analysis conditions. In the survey calculations, we calculated the criticality, burn-up reactivity, control rod worth, breeding ratio, assembly-wise power distribution, maximum linear heat rate, sodium void reactivity, and Doppler coefficient for the equilibrium operation cycles. The accuracy of the low-cost calculations was evaluated by measuring the agreements with the referential detailed conditions.
