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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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Fusion Science and Technology
Latest News
Steam is a sign of cooling system function . . . at ITER
Steam from one of ITER’s ten induced-draft cooling cells offers visual confirmation of a successful cooling system test, the ITER organization announced April 30. ITER’s cooling system features 60 kilometers of piping with pumps, filters, and heat exchangers that can pull water through at up to 14 cubic meters per second. Once fully operational, two cooling loops—one to remove the heat generated by the plasma in the ITER tokamak and one for its supporting infrastructure—will be capable of extracting up to 1,200 MW of heat.
Daeseo Koo, Jungmin Lee, Jongchul Park, Hyun-Goo Kang, Min Ho Chang, Sei-Hun Yun, Seungyon Cho, Ki Jung Jung, Seungwoo Paek, Hongsuk Chunga
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 435-438
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T48
Articles are hosted by Taylor and Francis Online.
Korea has been developing nuclear fusion fuel storage and delivery system (SDS) technologies including a basic scientific study on hydrogen storage. To develop nuclear fusion technology, it will be necessary to store and supply hydrogen isotopes needed for Tokamak operation. SDS is used for storing hydrogen isotopes as a metal hydride form. We designed and fabricated a small-scale getter bed of zirconium cobalt (ZrCo). The rapid hydriding of tritium is very important not only for safety reasons but also for the economic design and operation of the SDS. The effect of the initial absorption temperatures on the hydriding of ZrCo was measured and analyzed. The experimental results of the hydrogen pressure of hydriding (ZrCoH2.8) at various cooling temperatures are in agreement with the calculated values using numerical modeling equations. The effect of a helium blanket on hydriding was measured and analyzed. The experimental results of the hydriding with 0 %, 4%, and 8% of helium concentration are in agreement with the calculated values based on numerical modeling equations.