Title :
Neutronics Analysis of a Molten Salt Blanket for the HAPL Laser Fusion Power Plant with Magnetic Intervention
Author :
Sawan, M.E. ; Aplin, C.S. ; Sviatoslavsky, G. ; Raffray, A.R.
Author_Institution :
Univ. of Wisconsin, Madison
Abstract :
A blanket concept made of SiC/SiC composite and utilizing Flibe as coolant and tritium breeder has been developed and integrated with the magnetic intervention system. To achieve tritium self-sufficiency, a 1 cm thick Be insert is utilized in the first wall coolant channel. All magnet, vacuum vessel, and personnel shielding requirements can be satisfied. The nuclear performance parameters of this blanket were compared to those of a lithium-lead blanket in two chamber core configurations. Because of the lighter blanket and shield weight that needs to be supported, the higher thermal power, and the lower electrical conductivity, the Flibe blanket option is particularly well suited for a laser fusion power plant with magnetic intervention.
Keywords :
electrical conductivity; fusion reactor blankets; laser fusion; lithium compounds; neutron effects; shielding; silicon compounds; tritium handling; HAPL laser fusion power plant; Li2BeF4; SiC-SiC; core configurations; electrical conductivity; lithium-lead blanket; magnetic intervention system; molten salt blanket; neutronics method; shielding; size 1 cm; thermal power; tritium breeder; vacuum vessel; wall coolant channel; Coolants; Laser fusion; Magnetic analysis; Magnetic cores; Magnetic shielding; Personnel; Power generation; Power lasers; Silicon carbide; Thermal conductivity; laser fusion; magnetic intervention; neutronics; nuclear heating; shielding;
Conference_Titel :
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
978-1-4244-1193-1
Electronic_ISBN :
978-1-4244-1194-8
DOI :
10.1109/FUSION.2007.4337949
