Nuclear performance analyses of the HCLL breeder blanket for a fusion power reactor

This paper summarizes results of a neutronic study on the performance of the helium-cooled lithium–lead (HCLL) blanket for a fusion power reactor. The analysis is based on three-dimensional radiation transport calculations with the Monte Carlo code MCNP-4C. The neutronic model based on the PPCS reactor model AB developed by FZK has been used in the analysis. Nuclear performance parameters such as the tritium breeding ratio and the energy deposition rate in the blanket and shield and their radial distributions have been evaluated. The radiation-induced displacement and the helium gas production in the steel structure has been calculated. It was shown that the blanket configuration considered provides TBR greater than the required design value. The gaps between blanket modules was shown to affect the global TBR only insignificantly. The radiation damage assessment has indicated that the HTS could not be designed as a life-time component of the reactor for the anticipated 40 years of plant operation.