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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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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Nuclear News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
Woan Hwang, Cheol Nam, Thak Sang Byun, Young Cheol Kim
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 130-141
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2887
Articles are hosted by Taylor and Francis Online.
Computational models for analyzing in-reactor behavior of metallic fuel pins in liquid-metal reactors under steady-state conditions are developed and implemented in the Metal fuel performance Analysis (computer) Code for Simulating the In-reactor behavior under Steady-state conditions (MACSIS). Sodium logging and constituent redistribution effects are considered in calculating the temperature profile. The model for the radial redistribution of the fuel constituent is based on the thermotransport theory. The fission gas release model takes multibubble size distribution into account to characterize the lenticular bubble shape and the saturation condition on the grain boundary. Finally, the clad strains are calculated from the amount of fission gas released and interface pressure. Sample calculations are performed to verify each model. The results show that in general, the predictions of MACSIS agree well with the available irradiation data.