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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Nuclear’s moment: The ANS Annual Conference opens in the Mile-High City
The nuclear community descended on Denver, Colo., this week for the American Nuclear Society’s Annual Conference, which opened with a packed room and inspiring words from multiple speakers.
Linfeng Yan, Dawei Wang, Hsingtzu Wu
Nuclear Technology | Volume 208 | Number 12 | December 2022 | Pages 1822-1831
Technical Paper | doi.org/10.1080/00295450.2022.2083750
Articles are hosted by Taylor and Francis Online.
A passive residual heat removal system plays an important role in cooling the reactor core under accident conditions. The computational fluid dynamics (CFD) software package ANSYS Fluent is used to analyze the influence of malfunction of any 2 of 12 tubes of a passive residual heat removal heat exchanger (PRHR HX) on its performance. Then the computation was validated using the published experimental data. Five different scenarios and a normal condition are computed to analyze the influence of locations of the malfunctioning tubes on the heat transfer performance of the PRHR HX. The results show that the tube defect reduces the amount of heat transferred by the PRHR HX. However, it is correlated with the size of the surface area of the deficient tubes instead of their locations. In other words, analysis suggests that defect tubes with the same surface area should result in similar damage regardless of the location.