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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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.
U.Besserer, R.-D.Penzhorn, R.Brandt
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 793-796
Hydride and Storage | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22693
Articles are hosted by Taylor and Francis Online.
The Tritium Storage facility of the Tritium Laboratory Karlsruhe (TLK), was recently upgraded by four additional uranium beds and one containing ZrCo. Now it is possible to compare under very similar conditions the sorption/desorption properties of uranium and those of ZrCo. To test the adequacy of ZrCo for routine, the getter was folly disproportionated repeatedly using either protium, deuterium or tritium. In all cases was it possible to completely restore the original sorption/desorption properties of the getter. In view of the needs of the Storage and Delivery System (SDS) of the ITER-FEAT Tritium Plant, i.e. delivery of T2 90% - D2 10% and pure D2 to generate mixtures of various compositions, the isotope effects during sorption/desorption cycles of H-D and D-T mixtures in ZrCo granules have been investigated. A transportable storage vessel identical to those containing uranium presently used at TLK for the transport of tritium has been designed, build and filled with ZrCo. These beds fit into the highly sensitive calorimeters available at TLK. With these beds the tritium permanently trapped in U and ZrCo can be compared under similar operation conditions.
