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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
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.
Walter E. Clark
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 215-221
Technical Paper | International Safeguard / Chemical Processing | doi.org/10.13182/NT77-A31928
Articles are hosted by Taylor and Francis Online.
Radioactive iodine wastes can be isolated in very concentrated form as insoluble barium io-date in concrete. Specimens containing from 2.9 to 11.9% by weight of iodine as barium iodate have been prepared and subjected to standard leaching tests with very satisfactory results. Incremental rates after 100 days leaching were ∼3 μm/day for specimens containing 9.05% iodine; specimens containing from 5.4 to 11.9% iodine showed surprisingly comparable leach rates. Lower leach rates can be obtained by the addition of butyl stearate or by treating the concrete with waterrepellent agents. The process as envisioned produces no contaminated waste side streams. A product containing 9.05% fission product iodine, of which ∼75% is 129I, will generate ∼3.3 μW/kg of product. The daily iodine product from a 5 × 103 kg/day liquid-metal fast breeder reactor fuel reprocessing plant can be contained in 9.49 × 10−3 m3 (0.335 ft3) of such concrete.
