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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.
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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott Downtown
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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Viorel Fugaru, Cristian Postolache, Maria Gheorghe, Lidia Radu, Nastasia Saca
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 286-289
Technical Paper | doi.org/10.1080/15361055.2017.1293444
Articles are hosted by Taylor and Francis Online.
The study was conducted in order to determine the immobilization performance of low-level tritium waste in new cement mixtures. The grouts analyzed are fine mortars, fluid, self- compacting, with flowability, able to fill the smallest gaps in the solid waste container. The grouts curing showed compact and structural integrity without pores and cracks, so as to ensure radioactive tritium waste encapsulation.
Two types of solid/liquid tritium radioactive waste with known tritium activity have been prepared: one type containing a hydrophilic tritium compound and the other one a hydrophobic tritium compound.
The tritium waste was mixed with three different types of grout and poured in a cylindrical mould. The leaching of tritium from waste solidified/encapsulated in the cement mixtures immersed in an aqueous environment has been studied in order to select the most appropriate grout type as waste immobilization matrix.
Samples from the liquid surrounding the cements blocks were collected at predetermined time intervals and placed in the liquid scintillation cocktail and measured. The activity of the tritium released was then calculated.
