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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Tuomo Sevón
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 171-179
Technical Paper | doi.org/10.13182/NT16-108
Articles are hosted by Taylor and Francis Online.
The water ingression mechanism can enhance the coolability of a pool of molten corium in containment during a severe accident. A water ingression model was added to the MELCOR code in 2015. The purpose of this work was to test the new model. It was found that the water ingression model performed satisfactorily in core-concrete–interaction experiments in which gas bubbles were released to the melt from decomposing concrete. The new model had little effect in the Small-Scale Water Ingression and Crust Strength (SSWICS) experiments that were done without gas bubbling through the melt. When applied to the Fukushima Daiichi Unit 1 accident, the water ingression model slowed down concrete ablation by 19% but did not quench the melt. Because the water ingression model was added to MELCOR so recently, the default treatment is still to use multipliers for the boiling heat transfer coefficient and thermal conductivity instead of the proper water ingression model. These default parameters significantly overestimated melt coolability in all the experiments that were calculated.