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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Excelsior University student section awarded community education grant
The American Nuclear Society Student Section at Excelsior University in Albany, N.Y., was awarded a $5,000 grant from the ANS Student Section Strategic Fund initiative for its program, Empowering Tomorrow’s Nuclear Innovators: A Collaborative Approach to Nuclear Technology Education and Awareness.
Oleg G. Povetko
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 31-37
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3967
Articles are hosted by Taylor and Francis Online.
Radioactive waste-handling operations at a potential high-level radioactive waste (HLW) geologic repository at Yucca Mountain, Nevada, would involve receiving, processing, aging, and emplacing HLW equivalent to 70 000 t of heavy metal. This paper presents results of an independent analysis of the external radiation dose fields for various designs at a potential repository underground facility, performed at the Center for Nuclear Waste Regulatory Analyses. In order to analyze dose fields, radiation source terms have been developed for commercial spent nuclear fuel (SNF) assemblies. Full-scale three-dimensional models of waste packages and underground repository drifts were used in the Monte Carlo radiation transport simulations. Radiation dose rates along the drifts have been evaluated for multiple waste packages for SNF-emitted photons, neutrons, and 60Co photons. Analysis shows that SNF photons contribute >68%, 60Co photons contribute <30%, and neutrons contribute <2% to the total dose rates. The contribution of photons scattered off the drift walls is <10% of the total dose rates. The drift elbow significantly blocks direct radiation shine and reduces scattered dose rates at the junction of turnout and main access drifts where workers could be present.