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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Arkadiy A. Yukhimchuk, Vladimyr A. Arkhangel'sky
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 826-830
Design and Model | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22700
Articles are hosted by Taylor and Francis Online.
This paper presents a schematic design of Tritium Fuel Cycle for Muon-Catalyzed Intense Neutron Source (MC INS) capable of producing monochromatic 14 MeV neutrons. Based on the assumption that the fuel mixture should be used in a liquid phase the different approaches are proposed to incorporate a DT cell (synthesizer) into the MC INS facility The estimations of total tritium inventory in ihe MC INS facility are given. The calculations of the DT cell operation temperature regime using the code FLOW 3D are presented. It is shown the capability to remove the thermal energy released in the DT cell of the proposed design. The MC INS design is analyzed from the viewpoint of tritium safety requirements.