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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.