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2020 ANS Virtual Winter Meeting
November 16–19, 2020
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Fusion Science and Technology
U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Cyra Neugebauer, Y. Hörstensmeyer, C. Day
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 215-220
Technical Paper | dx.doi.org/10.1080/15361055.2019.1704139
Articles are hosted by Taylor and Francis Online.
One of the main design drivers of the EU-DEMO fuel cycle is to avoid unnecessary hydrogen isotope separation. In the tritium plant, this implies a novel functionality for isotope rebalancing (IR) and protium removal (PR). The task of IR is to adjust the deuterium-tritium ratio by several percent gradually over time in order to establish the required fuel mixture composition before reinjection into the torus. The PR is needed to process and separate protium, which inevitably enters the system via outgassing or replacement reactions. The candidate technology for the IR/PR function is temperature swing absorption, which is based on anticyclical operation of two absorption columns with reversed isotope effects. In order to characterize the separation process, a new test rig has been designed and is currently being assembled. This paper describes the principle idea of the process, develops a model to predict the performance, and presents simulation results for a DEMO-relevant gas composition. Palladium and vanadium have been selected for the modeling. It is shown that at the end of one column tritium could be separated with 92.5% purity. At the other column, protium with 46.4% and deuterium with 44.8% purity could be removed. A subsequent parameter study showed that the ideal gas supply would be 40% of the total length of the column and that 22 was the optimal number of cycles before extraction.