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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
Argonne opens registration for D&D training course
Registration is open for Argonne National Laboratory’s Facility Decommissioning Training Course, a four-day instruction designed for those responsible for the decontamination and decommissioning of nuclear facilities and who are looking to understand the full breadth and depth of the D&D processes.
The next session will be held July 16–19 in Santa Fe, N.M. Information on the course and how to register can be found here.
Akihiro Suzuki, Juro Yagi, Masaru Nagura, Daisuke Komiyama, Takayuki Terai
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 295-299
Fusion Technology Facilities | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14150
Articles are hosted by Taylor and Francis Online.
A PbLi thermal convection loop with the flow rate of a few centimeters per second was designed and constructed to perform an in-situ tritium release experiment in a neutron source of the YAYOI reactor of The University of Tokyo. Tritium was generated by the nuclear reaction of Li with neutrons released through a 1-mm-thick steel tube and followed the reactor power with some time lag, which was affected by the hydrogen concentration in the sweep gas. The overall permeation rate coefficients, around 10-5 m/s, were almost the same as those acquired in former works performed in static tests. Formation or reduction of a surface oxide layer on the permeation tube would affect the tritium release behavior.