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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Minghui Chen, Xiaodong Sun (Univ of Michigan), Richard N. Christensen (Univ of Idaho)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 835-843
Printed circuit heat exchangers (PCHEs) are promising to be employed in high-temperature gascooled reactors (HTGRs) due to their compactness and intrinsic characteristics of capable of providing high-temperature and high-pressure heat for industrial applications. In our previous study, a reduced-scale zigzag-channel PCHE was fabricated out of Alloy 617 and its heat transfer and pressure drop characteristics were investigated experimentally in a high-temperature helium test facility. In our current study, a computational fluid dynamics (CFD) code, STAR-CCM+, was used to simulate the thermalhydraulic performance of the fabricated PCHE with a simplified geometry model. Comparisons between the experimental data and the CFD simulations showed some discrepancies in the pressure drop and heat transfer results, which may be caused by the use of different thermal boundary conditions in the simulations from those in the experiments. The simplified heat exchanger simulation model was divided into eight segments to identify the thermal boundary conditions for the zigzag-channel PCHE. The temperature and heat flux distributions along the fluid flow direction in the heat exchanger for each segment were obtained. It was observed that the temperatures were not constant along the azimuthal direction of a cross section of the flow channel and the helium temperature distribution for each segment presented a wavy shape. However, the global helium temperature distribution along the entire flow channel was approximately linear. For the heat flux distributions, although they were significantly different at different segments, the trend for the heat flux for each segment along the fluid flow direction was similar.