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Division Spotlight
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.
Meeting Spotlight
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
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.
Athena A. Sagadevan, Sunil S. Chirayath
Nuclear Technology | Volume 208 | Number 3 | March 2022 | Pages 428-436
Technical Paper | doi.org/10.1080/00295450.2021.1922259
Articles are hosted by Taylor and Francis Online.
Until a long-term solution is finalized, interim storage of sufficiently cooled spent nuclear fuel (SNF) assemblies in dry casks is the predominant practice. Since these dry casks can contain approximately 160 kg of reactor-grade plutonium, they require safeguards monitoring. Results of a simulation study conducted on the design development and analysis of a remote monitoring system (RMS) are presented. The goal of the study was to determine the suitability of this RMS to meet the SNF monitoring objectives. MCNP simulations of a dry cask with all its contents and a set of simulations with one or two removed SNF assemblies were performed to test the detection capabilities of the RMS. The removed assemblies were substituted with dummy assemblies to simulate concealment. The studies showed that the RMS design is suitable to monitor and detect the removal of even a single SNF assembly from the cask.