The MCNPX Monte-Carlo particle transport code [1] coupled to the CINDER’90 depletion code [2]
has been used to compute the radioactive inventory of the EURISOL 4 MW power target [3].
At the very beginning, a benchmark study of the MCNPX code allowed us to choose the “best” spallation
and fission-evaporation model parameters for simulation. In this way some uncertainty estimates of
the presented results could be obtained. In this work we report an extensive list of nuclides
(given in Appendix) produced in the liquid mercury converter, for which detailed simulation were
done taking into account the realistic target geometry and material configurations.
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