Abstract
Different neutron data libraries frequently used in reactor pressure vessel dosimetry and related applications were compared and tested using activation measurement data from the international interlaboratory ex-vessel experiment at the Russian type pressurized water reactor Balakovo-3. Besides different data for the neutron transport calculations also different dosimetry cross section files were investigated. At simple testing models the impact of frequently used group approximations on neutron and gamma fluence parameters was studied by comparison of DORT and MCNP calculation results. The fast neutron results relevant for pressure vessel embrittlement agree reasonably for different libraries and calculation methods but the results for low energy neutrons as well as for deep penetrations differ strongly in many cases.
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