| Issue |
EPJ Web of Conferences
Volume 59, 2013
IFSA 2011 – Seventh International Conference on Inertial Fusion Sciences and Applications
|
|
|---|---|---|
| Article Number | 11005 | |
| Number of page(s) | 4 | |
| Section | XI. IFE Power Plant Technologies (Including Material Studies) | |
| DOI | https://doi.org/10.1051/epjconf/20135911005 | |
| Published online | 15 November 2013 | |
https://doi.org/10.1051/epjconf/20135911005
Studies of a self-cooled lead lithium blanket for HiPER reactor
1 Instituto de Fusión Nuclear, UPM/UNED, C/Jose Gutiérrez Abascal 2, Madrid, Spain
2 Dept. de Ingeniería Energética, ETSII, UNED, C/ Juan del Rosal 12, Madrid, Spain
3 Dept. de Ingeniería Mecánica, ETSII, UNED, C/ Juan del Rosal 12, Madrid, Spain
Published online: 15 November 2013
Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall – Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates.
© Owned by the authors, published by EDP Sciences, 2013
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