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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
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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January 2024
Latest News
Eisenhower’s “Atoms for Peace” at 70
Seventy years ago to the day, President Dwight D. Eisenhower gave his historic address to the United Nations General Assembly in New York City. (See December 2023 Nuclear News's “Leaders” column to read the reflections of Kathryn Huff, the Department of Energy’s assistant secretary for nuclear energy, on the speech’s anniversary.)
Hiroki Shishido, Noritaka Yusa, Hidetoshi Hashizume, Yoshiki Ishii, Norikazu Ohtori
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 382-388
Technical Paper | doi.org/10.1080/15361055.2017.1330623
Articles are hosted by Taylor and Francis Online.
The present study evaluates the thermal design of a blanket system using Flinabe in order to facilitate further discussions on its applicability as a self-cooled liquid blanket system. Molecular dynamics simulations were performed to evaluate the Prandtl number of mixtures in five compositions (LiF–NaF–BeF2 = 31–31–38, 36–27–37, 42–22–36, 49–16–35, and 67–0–33). Thermofluid analysis was carried out to estimate the temperature margin and pressure drop per unit length in a simple geometry model of the blanket system. The Prandtl number of Flinabe is above 100 at 400°C. The present study reveals that Flinabe remarkably relaxes the design conditions compared to Flibe as a coolant owing to its low melting point. In contrast, the pressure drop per unit length of Flinabe is higher than that of Flibe because the viscosity exponentially increases at low temperature. The temperature margin is quite dependent on the heat load on the first wall. If the pressure drop per unit length is around 1.0 MPa/m, the heat load value must be approximately below 0.7 MW/m2.