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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.
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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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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Ki-Seob Sim, Ho Chun Suk, Young Ku Yoon
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 351-365
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34719
Articles are hosted by Taylor and Francis Online.
The KFGR-T computer model has been developed to predict transient fission gas release from UO2fuel with an emphasis on the nonequilibrium behavior of fission gas bubbles. It takes into account the relevant physical processes generally considered by other workers, as well as migration of fission gas bubbles through channels formed by the extension of dislocations to grain boundaries during the transient heatup stage, grain growth/grain-boundary sweeping during the isothermal annealing stage at high temperatures, and gas release through intergranular cracking. This computer model is applied to calculate transient fission gas releases, and the calculated values are compared with the results of out-of-pile experiments performed with UO2 fuel base-irradiated to burnups in the range of 18 to 35 MW·d/kg U. The absolute values and the trends of the fission gas releases calculated with the KFGR-T model are in good agreement with the experimental data. A parametric study is also done to investigate the sensitivity of the model to variables such as initial grain size, heating rate, temperature gradient, and initial gas concentration, and these results are compared with the sensitivity of other models.