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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
August 2024
Latest News
Advanced nuclear workshop brings together Japanese and American experts
Tohoku University in Sendai, Japan, was the site of an advanced nuclear reactor workshop in late May that was hosted by the Fastest Path to Zero Initiative of the University of Michigan and Tohoku’s Center for Fundamental Research on Nuclear Decommissioning. The event was co-organized by the U.S. Consulate in Sapporo, Japan, and the Atlantic Council, which is associated with the North Atlantic Treaty Organization. The workshop, “The Potential Contribution of Advanced Nuclear Energy Technologies to the Decarbonization and Economic Development of Japan and the U.S.,” featured numerous American and Japanese academic authorities, government policymakers, executives of utilities and advanced reactor developers, and leaders of nongovernmental organizations. Also participating were students from both the University of Michigan and Tohoku University.
J. M. McDonald et al.
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 554-558
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST47-554
Articles are hosted by Taylor and Francis Online.
The molten salt Flibe, a combination of lithium and beryllium fluorides studied for molten salt fission reactors, has been proposed as a breeder and coolant for fusion applications. The melting points of 2LiF-BeF2 and LiF-BeF2 are 460°C and 363°C, but LiF-BeF2 is rather viscous and has less lithium for breeding. In the Advanced Power Extraction (APEX) Program, concepts with a free flowing liquid for the first wall and blanket were investigated. Flinabe (a mixture of LiF, BeF2 and NaF) was selected for a molten salt design because a melting temperature below 350°C appeared possible and this provided an attractive operating temperature window for a reactor. To confirm that a ternary salt with a low melting temperature existed, several combinations of the fluoride salts, LiF, NaF and BeF2, were melted in a stainless steel crucible under vacuum. One had an apparent melting temperature of 305°C. The test system, preparation of the mixtures, melting procedures and temperature curves for the melting and cooling are presented along with the apparent melting points. Thermal modeling of the salt pool and crucible is reported in an accompanying paper.