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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Roger Bonniaud
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 449-460
Technical Paper | Radioactive Waste | doi.org/10.13182/NT77-A31810
Articles are hosted by Taylor and Francis Online.
Les solutions concentrées de produits de fission, résidus du retraitement des combustibles irradiés, constituent une des sources les plus importantes des déchets produits par l’industrie nucléaire. Leur solidification par vitrification est la solution actuellement retenue par la France. Les procédés de solidifications, qui ont été développés en France sont les suivants: un procede de vitrification en pot et un procédé continu qui combine un calcinateur rotatif à un four de fusion de verre. En général, les verres utilisés en France sont à structure silicieuse, structure plus stable que la structure phosphatique. Le problème de la séparation de phases molybdiques dans les verres à forte concentration en produits de fission est resolu par l’augmentation de la concentration en B2O3 Pour le cas des solutions issues du combustible U-Mo, où la concentration en molybdène atteint 100 g ℓ−1 , l’addition d’alumine réduit la séparation de phase, conduisant à un solide à forte phase vitreuse. Des mesures des taux de lixiviation à l’eau naturelle avaient montré des résultats qui s’étendaient de 10−1 g cm−2 jour−1 à 10−6 g cm−2 jour−1 pour les compositions silico-boratées. Pour étudier le problème posé par les emetteurs α dans les verres, des blocs de verre étaient dopes avec différents emetteurs α qui, en 1 an développaient des energies equivalents aux energies libérées pendant 10 à 1000 ans de stockage des verres réels. The current approach in France to the problem of waste management of the solutions of concentrated fission products from fuel reprocessing is solidification by vitrification. The solidification processes utilized are a batch process, in-pot vitrification, and a continuous process, a rotary kiln calciner. Generally, a silicate glass that is more stable than the phosphate is used. The problem of separation of a molybdate phase at high fission product concentration is reduced by an increase in B2O3 concentration. For wastes from a U-Mo fuel that contains 100 g/ℓ of molybdenum, phase separation is reduced by addition of Al2O3. Leach rates for the borosilicate glass were studied, and rates of 10−8 to 10−6 g/cm2 per day were measured as a function of Na2O concentration. Plutonium leach rates were measured as a function of Na2O concentration. Plutonium leach rates were measured as 10−8 to 10−7 g/cm2 per day and 241Am was 8 × 10−9 g/cm2 per day after 110 days of leaching. Stability of the glasses to alpha-particle radiation damage was simulated for a storage period of 10 to 1000 yr. These samples indicated only a slight change in viscosity as a result of these simulation studies.