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Division Spotlight
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.
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.
Douglas W. Croucher
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 45-57
Technical Paper | Fuel | doi.org/10.13182/NT80-A32555
Articles are hosted by Taylor and Francis Online.
Three pressurized water reactor type fuel rods that contained defects representative of those occasionally found in the cladding of commercial reactor fuel rods, that is, a hydrided region, a pinhole-type defect, and an axial crack, were tested under power ramp and power-cooling-mismatch conditions. Operation of the hydrided fuel rod in a power ramp caused a cladding rupture at the location of hydriding and degraded the thermal performance of the rod. Operation of all three defective rods for a short time in film boiling did not seriously aggravate the condition of the rods beyond that experienced by intact rods undergoing the same transient. Embrittlement of the cladding, however, was in excess of that found in intact rods. Although the defective rods withstood the stresses associated with the quenching of the cladding from high temperature film boiling conditions, two of the rods fractured during post-test handling under conditions where intact Zircaloy-clad fuel rods embrittled by oxygen absorption alone would not have fractured. Fuel washout occurred where large, open cladding defects were present. No molten fuel-coolant or molten fuel-cladding interaction was observed.