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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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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Tae-Sic Yoo, Steven M. Frank, Michael F. Simpson, Paula A. Hahn, Terry J. Battisti, Supathorn Phongikaroon
Nuclear Technology | Volume 171 | Number 3 | September 2010 | Pages 306-315
Technical Paper | Pyro 08 Special / Reprocessing | doi.org/10.13182/NT10-A10866
Articles are hosted by Taylor and Francis Online.
This paper presents results of experiments and modeling for ion exchange of LiCl-KCl-based molten salts with zeolite-A. The experiments examined the equilibrium distributions of various nuclear fuel fission products between the molten salt and zeolite phases. In addition to data that were collected in previous studies, new experiments were run using ternary salts (LiCl-KCl-YCl3, LiCl-KCl-LaCl3, and LiCl-KCl-PrCl3) and quaternary salts (LiCl-KCl-CsCl-NdCl3 and LiCl-KCl-CsCl-SrCl2). All contacting experiments were conducted at 500°C with a salt-zeolite contacting period of 24 h to allow for equilibrium to be reached. The developed equilibrium model assumes that there are ion-exchange and occlusion sites, both of which are in equilibrium with the molten salt phase. A systematic approach in estimating the total occlusion capacity of the zeolite-A was developed. The parameters of the model, including the total occlusion capacity of the zeolite-A, were determined from fitting the entire set of experimental data available between previous studies and the current one. Experiments involving ternary salts were used to estimate the parameters of the model, while those involving quaternary salts were used to validate the model.
