Neutronics of SiC-LiPb High Temperature Blanket for Tritium Production
Fusion Science and Technology / Volume 64 / Number 3 / September 2013 / Pages 599-603
Nuclear Systems: Analysis and Experiments / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 / dx.doi.org/10.13182/FST12-581
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This study evaluates tritium production and breeding behavior in a LiPb blanket module with the neutron transport code MCNP using nuclear cross-section data from FENDL-2.1 libraries. The calculation results suggest that a sufficient tritium breeding ratio (TBR) can be obtained in the SiC-LiPb blanket concept and therefore a proper integral experiment on LiPb with DT neutrons can be planned for a small test module. Also, TBR, neutron shielding and nuclear heating in the module were evaluated. With the results of TBR and results from actual neutron generation devices, we have proposed a plan for an integral experiment with a measurable tritium amount.
