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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 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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April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
H. Hashizume, K. Yuki, N. Seto, A. Sagara
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 892-896
Test Blanket Modules | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9023
Articles are hosted by Taylor and Francis Online.
By changing the composition ratio in Flibe to decrease its melting temperature, it becomes possible to design the TBM under the temperature design limits for ferritic steel. The accompanied demerit due to the increase in viscosity and degradation in heat transfer performance is overcome by introducing sphere-packed pipe as the first wall. The empirical correlation for heat transfer performance is derived for several sizes and materials of the spheres. Through the present analysis, there exist design windows for the Flibe TBM. This possibility is strongly linked to the demo reactor development since the structural material development for higher temperature condition can lead to the usage of Flibe with higher melting temperature and better heat transfer performance, which could be available under higher heat flux in the demo reactor.