STUDIED OF HCLL BLANKET DESIGN (HELIUM COOLED LITHIUM LEAD) BY USING MCNPX PROGRAM

• Main Author: ROSIDAH MAEMUNAH (NIM : 20214041), INDAH
• Format: Theses
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/22565
• Institution: Institut Teknologi Bandung

Fusion reactor using tritium-deuterium reaction is going to be a prolific source of 14.1 MeV (80% of the fusion energy) neutrons, which they will be escaped from plasma. The reactor features a major radius of 8.1 m and minor radius of 2.5 m. Thus, one of the parts of fusion reactor which is the important design is Blanket Module (BM). One of the two European blanket concepts is the Helium Cooled Lithium Lead (HCLL). The HCLL blanket uses Pb-Li as a neutron multiplier, Li as a breeder, and high pressure (8 MPa) He as a coolant. The purpose of this study is investigating feasibility of blanket reactor such as: neutron analysis, shielding efficiency, and tritium breeding capability which for achieving the value of TBR more than one which will assure the tritium self-sufficiency in steady state operation. MCNPX program with Monte Carlo was the tools for calculating this. Neutron flux was resulted by this simulation that was shown reactor did no leakage experience. And tritium production from breeding blanket will be optimal when breeding material utilizing was Pb-Li.