Design and simulation of a blanket module for TOKAMAK reactors

In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperature of helium as cooling gas never exceeded 530[Formula: see text]C and the tolerable temperature of beryllium was obtained at 650[Formula: see text]C. In the proposed design, it is adequate to enrich the 6Li to 40%.

Energy Crisis and Nuclear Fusion Power

Due to the rapid industrialization and luxurious life style of mankind all of the non renewable sources of energy are going to finish in near future. To address energy crisis problem it is necessary to search or invent long lasting new sources of energy which could run the world for long term. Here, in this article a attempt has been made to discuss a new source of energy called nuclear fusion process. Several methods made to produce energy from nuclear fusion process are tried to discuss here. Fusion power offers the prospect of an almost inexhaustible source of energy for future generations, but it also presents so far insurmountable scientific and engineering challenges. The main hope is centered on tokamak reactors which confine deuterium-tritium plasma magnetically. The Himalayan Physics Year 5, Vol. 5, Kartik 2071 (Nov 2014)Page: 131-136