Neutronic performance of two European breeder-insid-tube (BIT) blankets for DEMO : The helium-cooled ceramic LiAlO(2) with Be multiplier and the water-cooled liquid Li17Pb
A neutronic analysis has been performed on the latest blanket designs relative to helium-cooled ceramic BIT (with LiAlO(2) and Be multiplier) and the water-cooled liquid Li17Pb in cylindrical modules. The MCNP Monte Carlo code, supplied with a neutron data library derived from the European Fusion File (EFF), has been used in the analysis. A detailed and accurate description of the geometrical model has been performed, inserting the main reactor details and avoiding breeder material dilution inside the modules. TBR performance is low for the solid breeder BIT. CM Li17Pb blanket reaches sufficient TBR to rely on tritium self-sufficiency. Shielding properties, with respect to the toroidal field coils, have been estimated in a simplified model by means of the ANISN code.
Bibliographic Reference: Paper presented: 3rd International Symposium on Fusion Nuclear Technology, Los Angeles (US), June 27 - July 1, 1994
Availability: Available from (1) as Paper EN 38229 ORA
Record Number: 199410494 / Last updated on: 1994-11-28
Original language: en
Available languages: en