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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Botros N. Hanna, Nam Dinh, Igor A. Bolotnov (NCSU)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1125-1133
Nuclear reactor safety research requires analysis of a broad range of accident scenarios. The major and the final safety defense barrier against nuclear fission products release during severe accident is the containment. Modeling and simulation are essential to identify parameters affecting Containment Thermal Hydraulics (CTH) phenomena. The modeling approaches used in nuclear industry can be classified in two categories: system-level codes and Computational Fluid Dynamics (CFD) codes. System codes are not as capable as CFD of capturing and giving detailed knowledge of the multi-dimensional behavior of CTH phenomena. However, CFD computational cost is high when modeling complex accident scenarios, especially the ones which involve long-time transients. The high expense of traditional CFD is due to the need for computational grid refinement to guarantee that the solutions are grid independent. To mitigate the computational expense, it is proposed to rely on coarse-grid CFD (CG-CFD).
This work presents a method to produce a data-driven surrogate model that predicts the grid-induced local errors. Given the massive high-fidelity data that are produced by either experiments or high-fidelity validated simulations, a surrogate model is trained to predict the grid-induced local errors as a function of coarse-grid features.
The proposed method is applied on a three-dimensional turbulent flow inside a lid-driven cavity. The capability of the method is assessed by applying the trained statistical model on new cases that have different grid size and/or geometry (aspect ratio). The proposed approach is shown to have a good predictive capability.