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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
Xuan Ha Nguyen, Yonghee Kim
Nuclear Science and Engineering | Volume 189 | Number 3 | March 2018 | Pages 224-242
Technical Paper | doi.org/10.1080/00295639.2017.1394086
Articles are hosted by Taylor and Francis Online.
Detailed pin-by-pin core calculations are under development to replace the conventional assembly-based nodal methods. This research investigates a novel intrapin reconstruction procedure coupled with these pinwise calculations to obtain a detailed power profile within a fuel rod. The reconstruction process is based on the well-established form function (FF) method. In this paper, the fuel rod is geometrically divided into 40 equi-volume subsections where the intrapin power is reconstructed with corresponding heterogeneous FF. The intrapin homogeneous flux distributions are approximated by using the analytical solution of the two-group neutron diffusion equation with pinwise boundary constraints. Four types of constraints are considered to determine the flux shapes: surface-average net current, surface-average, corner-point, and volume-average cell fluxes. Therefore, six different combinations of the boundary constraints are separately evaluated for the intrapin power profile. All necessary information, including burnup-dependent FFs, homogenized group constants, reference power distribution, and pinwise boundary constraints, are predetermined from a high-fidelity Monte Carlo calculation. The numerical results demonstrate that the intrapin power can be retrieved for enriched and Gd-loaded fuel pins with reasonable accuracy, even at rodded conditions and in highly burned conditions of 10 and 30 GWd/tonne U. In addition, a sensitivity analysis is also performed to assess the feasibility of the proposed method when it is coupled with a pinwise calculation.