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Division Spotlight
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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
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.