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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Shiping Wei, Xinyu Sun, Haixia Wang, Jiangtao Jia, Zhibin Chen, Shichao Zhang
Fusion Science and Technology | Volume 76 | Number 7 | October 2020 | Pages 869-877
Technical Note | doi.org/10.1080/15361055.2020.1777668
Articles are hosted by Taylor and Francis Online.
The China Fusion Engineering Test Reactor (CFETR) tritium plant has to deal with a larger amount of tritium than ITER. The tritium source term is one of the key issues for safety assessment and operation of the CFETR. In this technical note, the preliminary estimation and safety analysis of the tritium source term for the CFETR tritium plant in normal operation have been performed on compliance with the ongoing plant design. The estimation method adopted is the system dynamics simulation performed by the Tritium Analysis program for fusion System developed by the Frontier Development of Science (FDS) team. The preliminary analysis results show that the storage and delivery system still stores the most amount of tritium. Until after 1 month of operation the plasma-facing material needs to be cleaned in the CFETR corresponding to the 600-g limit. Tritium losses, such as tritium permeation into the coolant and release to building rooms, are of a much smaller amount than tritium decay in the 2-week operation. It is worth noting that the tritium concentration somewhere in the tritium plant can be slightly more than 1 DAC (derived air concentration). These preliminary analysis results could provide some valuable references for the safety design and tritium management of the CFETR tritium plant.