Neutronic performance of two European breeder-inside-tube (BIT) blankets for DEMO: the helium-cooled ceramic LiAlO sub 2 with beryllium multiplier and the water-cooled liquid Li sub 17 Pb

• Published in: Fusion engineering and design Vol. 28; pp. 642 - 647
• Main Authors: Petrizzi, L, Rado, V
• Format: Journal Article
• Language: English
• Published: 01.03.1995
• ISSN: 0920-3796

In support of ENEA activity in the European Community Test Programme, neutron analysis has been performed on the two latest blanket designs: helium-cooled ceramic breeder-inside-tube (BIT) (with LiAlO sub 2 and Be multiplier) and water-cooled liquid Li sub 17 Pb in cylindrical modules (CM). The powerful MCNP Monte Carlo code was used (version 4.2). A detailed and accurate description of the geometrical model has been performed by inserting the main reactor details and avoiding breeder material dilution inside the modules. The tritium breeding ratio (TBR) performance is low for the solid breeder BIT blanket (with 10 ports 1.011) due mainly to low blanket coverage near the exhaust duct, and this solution should be revised. The CM Li sub 17 Pb blanket reaches a sufficient TBR (1.059, with ports) to rely on T self-sufficiency. Shielding properties, with respect to the toroidal field coils, have been estimated in a simplified model by means of the ANISN code, supplied with a nuclear data library consistent with that used by MCNP. The analysis suggests that a careful shield thickness/composition design should be used to ensure the shielding capability of the whole blanket plus shield system.