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.
D. Haas, J. van de Velde, H. Braun
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 100-108
Technical Paper | Material | doi.org/10.13182/NT79-A16178
Articles are hosted by Taylor and Francis Online.
In the Rapsodie-I experiment, two bundles, each containing 34 fast breeder reactor fuel pins, have been irradiated up to a peak burnup of 10.6 at.% and to a peak fast fluence (E > 0.1 MeV) of 6.65 × 1026 n/m2. One of the main objectives of this experiment was to evaluate the mechanical behavior of a bundle with spacer grids. Two types of spacer grid designs have been tested: namely, a brazed ferrule grid design and a honeycomb spot-welded grid design. The grid material was in every case niobium-stabilized austenitic stainless steel type W.Nr. 1.4981 in the annealed condition. The density and the dimensional measurements carried out on the spacer grids revealed that the geometrical changes in the grids were almost entirely due to material void swelling. In some cases, however, mechanical interactions between grids and wrapper tubes and also between fuel pins and grid cells have been emphasized. These interactions had no detrimental influence on the in-pile bundle behavior. The postirradiation mechanical tests carried out on the honeycomb spacer grids showed that the mechanical properties of the grid cells have not been significantly altered by the irradiation. A decrease of the grid material Young’s modulus has been correlated with void swelling. It has been concluded that the spacer grids operated satisfactorily despite their severe loading conditions.
