Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors
Author:
Affiliation:
1. Massachusetts Institute of Technology Nuclear Reactor Laboratory, 138 Albany Street, Cambridge, Massachusetts 02139
2. Kairos Power LLC, 707 West Tower Avenue, Alameda, California 94501
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2020.1829428
Reference66 articles.
1. Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat
2. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR)
3. Mass transport analysis for tritium removal in FHRs
4. Tritium Management and Control Using Carbon in a Fluoride-Salt-Cooled High-Temperature Reactor
5. Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward
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