Studied of Tritium Breeding Ratio on HCLL (Helium Cooled Lithium-Lead) Fusion Blanket by Using MCNP Program

Abstract

Abstract The fusion reactor using a tritium-deuterium reaction is going to be a prolific source of 14.1 MeV (80% of fusion energy) neutrons, which will release from the plasma. This reactor features a major radius of 8.1 m and a minor radius of 2.5 m. Thus, one part of the fusion reactor, which is a basic design is Blanket Module (BM). One of the two European blanket concepts is Helium Cooled Lithium Lead (HCLL). HCLL blanket uses Pb-Li as a neutron multiplier, Li as a breeder, and He as a cooler is in high pressure (8 MPa). The study goal is to investigate the feasibility of blanket reactors, such as neutron analysis, shield efficiency, and tritium breeding capabilities. This calculation was simulated to achieve TBR value more than one, which will assure tritium self-sufficiency in steady-state operations. The MCNP program with Monte Carlo is a tool for calculating this. The neutron flux produced by this simulation shows that the reactor does no leak. And the production of tritium from breeding blanket will be optimal when the utilizing of breeding materials is Pb-Li.