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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
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Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
M. E. Sawan
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 272-277
Technical Paper | doi.org/10.13182/FST13-717
Articles are hosted by Taylor and Francis Online.
The amount and type of gaseous and metallic transmutants produced in tungsten (W) when used as a plasma-facing armor in magnetic (MFE) and inertial (IFE) confinement fusion systems were determined and compared to those obtained following irradiation in fission reactors. Up to ∼8% metallic transmutants are generated at the expected lifetime of the fusion blanket. Irradiation in fission reactors to the same fast neutron fluence yields a much larger amount of metallic transmutation products than in fusion systems. While the dominant component in fusion systems is rhenium (Re), osmium (Os) is the main transmutation product in fission reactors. The impact on the W properties needs to be assessed. The results of this work will help guide irradiation experiments in fission reactors to properly simulate the conditions in fusion systems by possible direct implantation of transmutation products in irradiated samples. In addition, the results represent a necessary input for modeling activities aimed at understanding the expected effects on properties.