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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.
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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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Timothy S. Roth, A. Biancheria
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 50-59
Technical Paper | Material | doi.org/10.13182/NT87-A33951
Articles are hosted by Taylor and Francis Online.
A computer graphics technique was used to measure cracks and other features of mixed-oxide fuel ceramographs to provide information useful for the modeling of fuel cracking and fragment movement. These measurements provided qualitative and quantitative information in several areas: crack formation and fuel-fragment movement, fuel-cladding gap size, crack size, crack orientation, radial distribution of crack porosity, and change in fuel volume (referred to as total fuel swelling) as a function of oxygen-to-metal ratio (O/M) and burnup. Examination of the ceramographs indicated that a crack starts on a free surface and propogates until it reaches another free surface. Thus, the first crack extends from one side of the fuel to the other, and succeeding cracks terminate on existing cracks or on the fuel surface. While crack formation was found to be independent of O/M, differences in crack healing at moderate power (19 kW/m) and high burnup (12 at.%) lead to a predominance of radial cracks for high O/M (∼1.96) fuel and both radial and circumferential cracks for low O/M (∼1.92) fuel. The different effects of circumferential and radial cracks on fuel behavior produce smaller postirradiation fuel-cladding gaps and larger cracks in the lower O/M fuel pins. Fuel swelling at intermediate burnup (∼8 at. %) is independent of O/M, but at high burnup (∼12 at. Vo) lower O/M fuel swells more. This swelling behavior may be related to a similar O/M dependence of retained fission gas.