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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Baiquan Deng, Zaixin Li, Jinhua Huang, Tao Yuan
Fusion Science and Technology | Volume 46 | Number 4 | December 2004 | Pages 548-560
Technical Paper | doi.org/10.13182/FST04-A590
Articles are hosted by Taylor and Francis Online.
A summary of the tritium system design activities for the engineering outline design of a fusion experimental reactor [Fusion Experimental Breeder-E (FEB-E)] is presented. This paper is divided into three sections. First, the geometry, loading features, and tritium concentrations in liquid lithium of tritium breeding zones in blankets are described. Then, a tritium flowchart corresponding to the tritium fuel cycle system is constructed, and the SWITRIM code is developed for calculation of the inventories in the ten subsystems. Results show that the necessary initial tritium storage to start up the reactor with fusion power of 143 MW is ~317 g. Finally, a tritium leakage analysis under different operation circumstances is performed. It is found that the potential danger of tritium leakage could result from the exhausted gas of the divertor system. It is important to elevate the tritium burnup fraction and reduce the tritium throughput.