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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.
Seul-Been Kim, Jaeho Lee, Goon-Cherl Park, Hyoung Kyu Cho (Seoul National Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 772-776
The necessity of the latest codes and methods for safety demonstration is increased to satisfy new safety requirement and achieve improved margin management. In this circumstance, it becomes an important issue that high-fidelity and multi-physics simulation with coupled T/H (Thermal-Hydraulics) and neutronics code for light water reactor whole core. With the improved computing power, the subchannel scale T/H analysis could be used as a suitable tool for pin-by-pin whole core simulation considering both accuracy of simulation and reasonable calculation time.
CUPID is a multi-dimensional two-phase flow analysis code developed by KAERI for the analysis of reactor core component. It has been validated against various experimental data and applied for practical nuclear applications. Recently, its applicability was extended to the subchannel scale T/H analysis. It is highly parallelized with the domain decomposition and message passing interface and these features facilitated the extension to use the code for the whole reactor core pipby- pin analysis in the subchannel scale. Required physical models for the subchannel scale analysis, for example, turbulent mixing and void drift models, were implemented and validated against available subchannel experiments.
In the present study, the grid spacer model was implemented for the enhancement of accuracy of the simulation. Afterwards, the mixing vane model was implemented considering lateral momentum exchange between adjacent subchannels by the mixing vane. For the validation of models, PSBT 5x5 experiment was simulated using CUPID, and the calculation result was compared with the CTF calculation. These implemented models can contribute to improve the prediction capability of CUPID for more realistic whole reactor core transient analysis.