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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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Latest News
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Enzo Curti, Matthias Krack, Daniel Grolimund (Paul Scherrer Inst), Sergey V. Churakov (Paul Scherrer Inst/Univ of Bern)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 281-285
The long-lived nuclide 79Se plays a key role in safety assessments for underground radioactive waste repositories. In general, Se is assumed to diffuse out of the fuel grains and to migrate toward the periphery of fuel pellets due to the high thermal gradient during LWR reactor operation, similarly to the volatile elements I and Cs. According to this model, a significant part of the 79Se inventory in spent fuel would be readily accessible to leaching after water ingress in the repository. However, contrary to these expectations, leach experiments did not show measurable Se release after exposing spent UO2 fuel samples to aqueous solutions during up to one year.
In order to explain this result, X-ray absorption near edge structure (XANES) spectra were measured on microsamples of high-burnup UO2 spent fuel from two light water reactors. The results indicate that Se occurs in the fuel as sparingly soluble, almost immobile Se(-II) ion (selenide). The occurrence of soluble oxidized forms of Se could be ruled out. Theoretical XANES calculations proved to be consistent with Se occupying oxygen sites in the UO2 crystal structure.
From these results we conclude that the release of 79Se from UO2 spent fuel in an underground repository will be controlled by the slow dissolution of the fuel matrix and not by early short-term release. Our spectroscopic data thus explain why dissolved Se was not detected in the leach experiments. Moreover, they are essential to reliably define critical source term parameters, specifically the "Instant Release Fraction" (IRF), in performance assessment calculations.