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.
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering