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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Shinya Chiba, Saburo Toda, Kazuhisa Yuki, Akio Sagara
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 779-783
Chamber Technology | doi.org/10.13182/FST01-A11963333
Articles are hosted by Taylor and Francis Online.
A molten salt FLiBe is proposed to be one of candidate materials for coolant and breeder in a fusion blanket. However, it is high Pr-number fluid with large viscosity. Therefore, applying it as the coolant for high surface heat flux conditions, we have to develop a new methods to enhance heat transfer of molten FLiBe flowing in a channel by an adequate active promoters. Through the present study of numerical analysis, it is clarified that an averaged Nusselt number of molten FLiBe laminar flow in a channel filled with the porous medium is higher than that in a normal smooth pipe. The larger enhancemnet can be increased with increasing flow velocity, however, the averaged Nu number shows a maximum value because the heat transfer in the radial direction perpendicular to the flow axis becomes relatively reduced with the increase of the flow velocity.