6533b871fe1ef96bd12d0dd5

RESEARCH PRODUCT

Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

Giuseppe VellaE. OliveriG. AielloL. Giancarli

subject

Materials scienceHelium gasbusiness.industryMechanical EngineeringWater cooledNuclear engineeringchemistry.chemical_elementBlanketNuclear physicsLead (geology)Nuclear Energy and EngineeringchemistryElectromagnetic shieldingNeutron sourceGeneral Materials ScienceLithiumPhotonicsbusinessCivil and Structural Engineering

description

Abstract The water-cooled Pb–17Li demonstration plant (DEMO) breeding blanket line was selected in 1995 as one of the two EU lines to be further developed in the next decade. In this paper the results of a neutronic and photonic analysis of the `single box' concept is presented. A full three-dimensional model, including the whole assembly and many of the DEMO reactor components, has been developed, together with a three-dimensional neutron source. A tritium breeding ratio (TBR) value of 1.16, with no ports and a Li6 enrichment of 90%, has been obtained and a further analysis has been performed to determine Li6 enrichment that would still ensure tritium breeding self-sufficiency. Selected power densities, calculated for the different materials and zones, are also presented. Material damage through displacements per atom and helium gas production has been investigated. Some shielding capability considerations are presented too.

yearjournalcountryeditionlanguage
1998-09-01Fusion Engineering and Design
https://doi.org/10.1016/s0920-3796(98)00149-5