Neutronic analysis for the EU water-cooled lithium-lead test blanket module in ITER-FEAT

Comprehensive neutronic analyses using the MCNP Monte Carlo code have been performed to predict the neutronics performance of the EU water-cooled lithium-lead test blanket module (TBM) integrated in ITER-FEAT. The analyses have been performed using models representing the complex ITER and TBM structure close to reality. Tritium generation and parameters relevant to the lifetime performance of the TBM such as helium, hydrogen and atomic displacement production have been calculated. Assuming 90% Li-6 enrichment and 22% duty cycle, the estimated tritium production amounts to 3.8738 x 10(16) T atoms s(-1), (16.62 mg d(-1)). The maximum radiation damage obtained, based on 0.3 MWa m(-2) neutron fluence, is in the first wall first steel layer of the breeder container totalling 2.77 dpa of Fe in Euro steel, 19.3 appm He production and 103 appm H generation. The calculated helium production in the demountable hydraulic connections of TBM is below the required limit for reweldability of steel structure.