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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Afiqa Mohamad, Yutaka Udagawa
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 245-260
Research Article | doi.org/10.1080/00295450.2023.2185061
Articles are hosted by Taylor and Francis Online.
In the Power to Melt and Maneuverability (P2M) project, a simulation exercise on two past power ramp experiments, xM3 on a medium-burnup rod and HBC4 on a high-burnup rod, was performed with the fuel performance code FEMAXI-8 to investigate fuel behavior under high-power and high-temperature conditions toward centerline fuel melting. In order to treat fuel melting, empirical melting temperature models have been incorporated into the FEMAXI-8 code. The present analysis gives reasonable predictions not only on cladding deformation but also on the fuel melting behavior of the HBC4 rod in which the UO2 liquidus temperature was reached during the transient. On the other hand, model improvement appears to be needed for a more accurate treatment of the fuel melting behavior of the xM3 rod in which the fuel center temperature reached the solidus line, whereas it may have not reached the liquidus line. A reasonable agreement of estimated fission gas release (FGR) with the measurement suggested that the high-temperature FGR at the given conditions is essentially a temperature-dependent phenomenon rate limited primarily by thermally activated elementary processes, such as fission gas diffusion.