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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Nominations open for CNTA awards
Citizens for Nuclear Technology Awareness is accepting nominations for its Fred C. Davison Distinguished Scientist Award and its Nuclear Service Award. Nominations for both awards must be submitted by August 1.
The awards will be presented this fall as part of the CNTA’s annual Edward Teller Lecture event.
Masoomeh Ghasemi, Jaeyoo Choi, Hyun-Goo Kang, Hyunchul Ju
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 404-414
Technical Paper | doi.org/10.1080/15361055.2020.1712994
Articles are hosted by Taylor and Francis Online.
The purpose of this study is to investigate the influence of design parameters for the scale-up of the depleted uranium (DU) bed. The actual DU bed chosen for this study has a DU loading of 1.86 kg for a tritium capacity of 70 g and is cylindrical in shape and equipped with copper foam to enhance internal heat transfer. Based on the reference DU bed geometry, three different scale-up bed geometries to increase the amount of DU loading up to 9.3 kg were designed under different aspect ratios for comparison purposes and simulated using a three-dimensional transient DU hydride model developed in our previous studies. The simulation results are compared in terms of the evolution of the DU hydride temperature and H/U atomic ratio during the DU hydriding process. This study helps to identify key design parameters (e.g., it is critical to scale up the DU bed geometry).