ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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August 2024
Fusion Science and Technology
Latest News
U.K., Japan step up progress toward fusion power demonstrations
Japan’s recent moves to boost fusion power in the nation’s energy plan and accelerate the timeline for a prototype fusion power plant come in response to increased global attention on fusion energy. Even as ITER faces delays, more than 40 private fusion developers are pursuing different technologies and competing for attention. And so are other countries, including the United Kingdom, which announced its plans for a fusion pilot plant back in 2019. Fusion companies and nations alike are responding to a growing sense that there is a race—or at least collective momentum—to commercialize fusion energy.
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.