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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
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.