Neutronic analysis of the European reference design of the water cooled lithium lead blanket for a DEMOnstration reactor
In this paper a neutronic analysis of the single box is presented. A full 3-D model including the whole assembly and many of the reactor details has been defined, together with a 3-D neutron source. A TBR value of 1.19 (no ports) confirms the tritium breeding self-sufficiency of the design. Selected power densities, calculated for the different materials and zones, are presented. Some shielding capability considerations with respect to the toroidal field coil system are also presented.
Bibliographic Reference: Paper presented: 18th Symposium on Fusion Technology, Karlsruhe (DE), August 22-26, 1994
Availability: Available from (1) as Paper EN 38632 ORA
Record Number: 199411316 / Last updated on: 1994-12-06
Original language: en
Available languages: en