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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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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.
David G. Martin
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 304-311
Technical Paper | Fuel | doi.org/10.13182/NT79-A32184
Articles are hosted by Taylor and Francis Online.
The fact that not all coated fuel particles in a batch fail after the same irradiation history is due to manufacturing variations in values of individual particle parameters. Two methods of calculating the failure fraction as a function of burnup in terms of these statistical variations are discussed: (a) a random sampling of particles combined with a simple stress model, and (b) the convolution of the individual variations combined with an advanced stress model. These methods were applied to particles manufactured by two laboratories in support of the U.K. low-enriched fuel cycle high-temperature reactor design. Experimental values of variations in the following parameters were included: kernel diameter and porosity, thickness of buffer, seal, silicon carbide and inner and outer pyrocarbon layers (all assumed to be normally distributed), and the silicon carbide fracture stress (assumed to obey a Weibull distribution). It was concluded that the convolution approach was the more satisfactory method. The results enable one to identify which of the various parameters considered are the most worthwhile for manufacturers to put development effort into so as to reduce their variability. For the particles considered here, these are primarily silicon carbide fracture stress, followed by kernel porosity.