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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Jae-Won Lee, Do-Youn Lee, Young-Soon Lee, Jae-Hwan Yang, Geun-Il Park, Jung-Won Lee, Hyoung-Mun Kwon, Yung-Zun Cho
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 101-109
Technical Paper | doi.org/10.1080/00295450.2018.1469347
Articles are hosted by Taylor and Francis Online.
Performance tests of mechanical decladding technology for estimating the feeding portions of the recovered fuel fragments to an electrolytic reduction process were conducted in terms of the fuel rod burnups of 27.3 to 65.7 GWd/tonne uranium (tU) for the used pressurized water reactor nuclear fuel. The decladding efficiencies with fuel burnups were quantitatively obtained from slitting decladding tests. Based on the average fuel rod burnups, fuel rods with an average burnup of up to 52.3 GWd/tU showed above 99%, but higher burnup fuels of above 54.9 GWd/tU were below 97.52% in the decladding efficiency. It was interpreted that variations in decladding efficiency with fuel burnups were closely linked to the opening characteristics of the gap between the pellets and cladding. However, the fuel fragment size distribution after slitting decladding has little difference in fuel burnup changes between 34.8 and 55.4 GWd/tU. Hence, feeding portions of the fuel fragments from an assembly basis by using the decladding efficiency and recovered fragment size distribution data were estimated with burnup variations of 35 to 52.5 GWd/tU.