ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
Russia withdraws from 25-year-old weapons-grade plutonium agreement
Russia’s lower house of Parliament, the State Duma, approved a measure to withdraw from a 25-year-old agreement with the United States to cut back on the leftover plutonium from Cold War–era nuclear weapons.
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.