Tritium Control for Flibe/V-Alloy Blanket System

• Published in: Fusion science and technology Vol. 52; no. 3; pp. 682 - 686
• Main Authors: Muroga, T., Tanaka, T., Li, Zaixin, Sagara, A., Sze, Dai-Kai
• Format: Journal Article
• Language: English
• Published: Taylor & Francis 01.10.2007
• ISSN: 1536-1055; 1943-7641
• DOI: 10.13182/FST07-A1568

One of the critical issues of Flibe/V-alloy blanket with REDOX control by Be is a large tritium inventory in V-alloy structures. Among the possible solutions to this issue would be to control REDOX not by Be but by addition of MoF 6 or WF 6 enhancing the reaction from T 2 to TF. The present study investigated feasibility of this procedure by thermodynamic and neutronics calculations. Using the blanket dimensions of Force Free Helical Reactor (FFHR), tritium inventory in V-alloy structure and Flibe were estimated based on the calculated equilibrium partial pressures of T 2 and TF in various cases of REDOX control by MoF 6 or WF 6 . Also carried out were neutronics examinations for the impact of Mo or W doping in the blanket. The results showed that the tritium inventory in the blanket area would be less than 100g at the TF level of 0.1 and 1 ppm in Flibe with addition of WF 6 and MoF 6 , respectively. WF 6 doping is far more advantageous than MoF 6 doping for low activation purposes.