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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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Nuclear Technology
Fusion Science and Technology
Latest News
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
Jae-Uk Lee, Min Ho Chang, Hyun-Goo Kang, Dong-You Chung, Sei-Hun Yun, Suh-Young Lee, In-Beum Lee
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1046-1052
Technical Paper | doi.org/10.1080/15361055.2019.1643688
Articles are hosted by Taylor and Francis Online.
This paper presents a dynamic model and simulation of the fuel delivery process between the separation system and the fueling system in the fusion fuel cycle considering the time-varying tokamak fuel demand. The fuel delivery process consists of vacuum pumps, valves, pressure vessels, and pipelines. Experimental data are applied to model the performance curves of the vacuum pumps. The delivery pressure is needed to be controlled to satisfy the pressure requirement of the fueling system. The developed dynamic model can be used to investigate delivery pressure fluctuation under various demand scenarios including a certain peak demand. The model is applied to the tritium delivery line during the inductive operation of the tokamak. Several rules for vessel switching are analyzed to examine the change of delivery pressure. The results show that the fluctuation can be reduced by switching vessels just before peak demand. The pressure fluctuation must be avoided by improving the flow coefficient of the control valve.