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.
Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
L. Barleon, L. Bühler, K.J. Mack, R. Stieglitz, B.F. Picologlou, T.Q. Hua, C.B. Reed
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2197-2203
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30045
Articles are hosted by Taylor and Francis Online.
In designing a self-cooled liquid metal blanket based on the poloidal-toroidal flow concept, the magnitude of the MHD pressure drop and the character of the velocity distribution in the first wall coolant channels, that result from 3-dimensional MHD effects associated with the required right angle bends in the coolant flow, represent important design issues. To address these issues and to verify the relevant models used in the design, a joint MHD-experiment was conducted by Argonne National Laboratory (AND and Kernforschungszen-trum Karlsruhe (KfK). The test article was designed and built at ANL, and the experiments were performed at KfK's MEKKA facility using a 3.6 Tesla superconducting solenoid magnet and a eutectic sodium potassium alloy working fluid. In the experiments, detailed voltage and pressure distributions on the duct walls and voltage distributions within the liquid metal were measured under a variety of Hartmann numbers and interaction parameters. Representative results from these measurements are presented and compared to analytical predictions valid for very high interaction parameters (inertialess flow). Results indicate that deviation between analysis and experiment is confined to the immediate vicinity of the right angle sharp corner and that, for fusion blanket conditions, the 3-dimensional pressure drop in the radial-toroidal bend of an electrically separated single channel is small compared with the pressure drop of the radial flow.