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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
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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
Finding fusion’s place
Fusion energy is attracting significant interest from governments and private capital markets. The deployment of fusion energy on a timeline that will affect climate change and offer another tool for energy security will require support from stakeholders, regulators, and policymakers around the world. Without broad support, fusion may fail to reach its potential as a “game-changing” technology to make a meaningful difference in addressing the twin challenges of climate change and geopolitical energy security.
The process of developing the necessary policy and regulatory support is already underway around the world. Leaders in the United States, the United Kingdom, the European Union, China, and elsewhere are engaging with the key issues and will lead the way in setting the foundation for a global fusion industry.
Yoshitaka Ueki, Yuya Noguchi, Juro Yagi, Teruya Tanaka, Takehiko Yokomine, Masaru Hirabayashi, Kuniaki Ara, Tomoaki Kunugi, Akio Sagara
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 530-536
Technical Note | dx.doi.org/10.1080/15361055.2017.1330636
Articles are hosted by Taylor and Francis Online.
The lead-lithium eutectic alloy (PbLi) is a promising coolant for nuclear fusion reactors. Although PbLi flow and heat transfer in a nuclear fusion reactor condition needs to be comprehended, no velocity profile measurement techniques have been developed yet. Since PbLi is a high-temperature liquid metal, ultrasonic Doppler velocimetry (UDV) is a promising method. In the present study, we investigated a UDV measurement in a high-purity PbLi forced convection loop environment. In summary, naturally contained oxide particles as flow tracers could differ by PbLi purity, and this difference could influence UDV measurability.
