Study on Fusion Blanket with Ceramic Solid as Tritium Breeding Material
Indah Rosidah, Zaki Suud, Abdul Waris, Dwi Irwanto
ITB
Abstract
This paper addresses the neutronic analysis in Helium cooled blanket. The blanket design is justified in ITER where illustrated in solid breeder blanket, so the breeder material considered is ceramic solid breeding material that will have to be tritium self-sufficient condition. The Li2O, LiAlO2, Li2ZrO3, Li4SiO3 and Li2TiO3 are candidate of ceramic solid breeder to be tritium breeder in fusion blanket systems. The blanket had to be designed by beryllium as neutron multiplier because its property minimized these neutron losses. The work presented using the Monte Carlo simulation MCNP that developed in Los Alamos National Laboratory (2010) to evaluate the tritium breeding capability. It investigated neutron thermalization and multiplier, tritium production methods, and tritium breeding requirement.
Keywords: Breeding, ceramic solid, fusion, Helium, tritium
Topic: Nuclear and Radiation Computation