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Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems

Wu, Xiao
http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907

Abstract Details

2016, Master of Science, Ohio State University, Nuclear Engineering.
The Fluoride salt-cooled High-temperature Reactor (FHR) is a Generation-IV molten salt reactor. However, tritium generation from neutron activation of the primary coolant FLiBe (a mixture of molten LiF and BeF2) is a significant issue in current development of FHRs. Currently a three-loop FHR is under consideration with an intermediate loop for tritium management. As the increased size and therefore the cost of FHRs brought by the additional loop offset the advantages of FHRs, a tritium control system that could be applied to a two-loop FHR is investigated in this study. In this paper, a tritium control and mitigation system is presented. It consists of three major facilities: the redox control facility, the tritium removal facility and the IHX with tritium permeation barrier. In addition, Al2O3 coating as a surface treatment on structural materials is applied as needed to prevent potential tritium leakage. The designs of the facilities are developed and optimized via computational simulation using COMSOL Multiphysics and MATLAB. The system proposed can achieve three major tasks. The first one is the control of TF existence in the primary coolant, which is highly corrosive to structural materials in the primary loop. The second task is the extraction of tritium from the primary coolant. It would be beneficial if the tritium extracted is collected for further use. The third task is the prevention or minimization of tritium permeation out of the primary loop through intermediate heat exchanger or structural materials.
Xiaodong Sun (Advisor)
Richard Christensen (Committee Member)
Lei Cao (Committee Member)
115 p.
Nuclear Engineering

Recommended Citations

Citations

  • Wu, X. (2016). Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems [Master's thesis, Ohio State University]. OhioLINK Electronic Theses and Dissertations Center. http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907

    APA Style (7th edition)

  • Wu, Xiao. Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems . 2016. Ohio State University, Master's thesis. OhioLINK Electronic Theses and Dissertations Center, http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907.

    MLA Style (8th edition)

  • Wu, Xiao. "Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled High-temperature Reactor Systems ." Master's thesis, Ohio State University, 2016. http://rave.ohiolink.edu/etdc/view?acc_num=osu1452249907

    Chicago Manual of Style (17th edition)

osu1452249907
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© 2016, all rights reserved.
This open access ETD is published by The Ohio State University and OhioLINK.