ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 514-520
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33176
Articles are hosted by Taylor and Francis Online.
Full-scale experimental measurements on the thermal effects of torch fires on a large spent nuclear fuel shipping cask have been obtained. The measured temperature data in the various materials of the multilayered cask are unique, since no torch tests have been previously performed on a cask. These data were obtained during a series of four torch tests that simulate a situation in which the relief valve of a liquefied gas tank railcar has been opened and the contents are vented and ignited so that the resultant torch impinges on the cask. An existing spent fuel cask was modified, and temperature data were obtained in the various materials of the multilayered cask using stainless-steel sheathed thermocouples. Results of these tests indicated that the surface temperatures for the cask with a voided neutron shield were about twice as high as those for a cask having a neutron shield filled with water. The wood in the impact limiter effectively prevented thermal penetration, limiting the temperature rise of the inner cavity to only 13°C in test 4. The maximum temperature rise of the inner cavity surface, which occurred in test 3 with the neutron shield voided, was 80°C. These thermal data will be used to refine a transient thermal analytical model, which can then be utilized to predict the thermal response of other nuclear material shipping system designs subjected to torch fire environments.