Water-cooled Pb-17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses

The Water-Cooled Lithium Lead (WCLL) DEMO blanket is one of the two EU line s to be further developed with the aim of manufacturing by 2010 a Test Blan ket Module for ITER (TBM). In this paper results of a 3D-Monte Carlo neutro nic analysis of the TBM design are reported. A fully 3D heterogeneous model of the WCLL-TBM has been inserted into an existing ITER model accounting f or a proper D-T neutron source; The structural material assumed for the cal culations was martensitic 9% Cr steel code named Z 10 CDV Nb 9-1. Results h ave been compared with those obtained using MANET. The main nuclear respons es of the TBM have been determined, such as detailed power deposition densi ty, material damage through DPA and He and H gas production rate, radial di stribution of tritium production rate and total tritium production in the m odule. The impact of using natural Lithium on the TBM system operation has also been evaluated. (C) 1998 Elsevier Science B.V. All rights reserved.