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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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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.
J. Bourges, C. Madic, G. Koehly, T. H. Nguyen, D. Baltes, C. Landesman, A. Simon
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 204-220
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT96-A35189
Articles are hosted by Taylor and Francis Online.
In 1985, the Commissariat à I’Energie Atomique (CEA), France, decided to set up an industrial unit at the Saclay Nuclear Research Center to produce fission 99Mo and to supply this isotope to the ORIS Company, France, for medical applications. The CEA’s role in this project was to develop a brand-new process for 99Mo production and to assume responsibility for the design and construction of the industrial plant. Production was based on 74 TBq (2 kCi) of 99Mo per week, under particularly severe constraints to protect the environment and the workers. The production unit, run in a semiautomatic mode, was built at Saclay in 1987 and cold tested from 1987 to 1989. The unit was never upgraded to active experiments because of the sudden drop in the price of 99Mo on the world market, which made the French project uneconomic. The focus here is mainly on the research conducted at the time to define and to validate the entire fission molybdenum chemical process. The process flowchart incorporates two original features. First, in the head-end of the process, the irradiated targets are dissolved in a sulfuric acid medium, entailing the maintenance of radioiodine and radiotellurium, for safety reasons, in the form of I‾(AgI) and Te(0), respectively, allowing their easy removal as solids from the dissolution liquors and their subsequent storage for radioactive decay. Second, in the core of the process, the molybdenum is purified by extraction with tri-n-butylacetohydroxamic acid, an extractant with exceptional affinity and selectivity for Mo(VI). The 99Mo(VI) extraction cycles employ the extraction chromatographic mode.