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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
S. Mori, H. Miura, S. Yamazaki, T. Suzuki, A. Shimizu, Y. Seki, T. Kunugi, S. Nishio, N. Fujisawa, A. Hishinuma, M. Kikuchi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1744-1748
Magnetic Fusion Reactor and Systems Studies | doi.org/10.13182/FST92-A29973
Articles are hosted by Taylor and Francis Online.
This paper describes the preliminary design of the steady state tokamak reactor (SSTR) blanket cooled by a mixture of helium gas and fine solid particles. Light yet highly heat resistant material, titanium aluminide (TiAl), is used as structural material. Thickness of tritium breeding blanket using lithiated ceramics and beryllium neutron multiplier is minimized and high-temperature and non-breeding shield blanket is installed to enhance blanket energy multiplication. It is found that TiAl is advantageous in radioactive waste management because the contact dose rate of TiAl first wall attenuates rapidly. The gas-particulate mixture coolant lowers the helium pressure to 5 MPa and reduces the volumetric flow rate when compared to a pure helium-cooled blanket. The net thermal efficiency larger than 40 % can be achieved with the outlet coolant temperature of 700°C.