Decay heat estimate based on EAF-2003 and FENDL/A-2 nuclear data libraries for fusion relevant materials in comparison with FNS-JAERI experiments

Results are presented on activation data analyses for materials of main relevance to fusion technology, referring to the activation data libraries EAF-2003 and FENDL/A-2 and to the FENDL/D-2 decay data library and to the relevant calculations performed with the European activation code ANITA-2000. The comparison is presented and discussed of these calculations with respect to integral decay heat measurements performed at the Fusion Neutronics Source FNS, JAERI, Tokai, Japan, with the aim to validate the same activation nuclear data by the adopted computational approach. The neutron flux distributions into the material samples were provided by JAERI as results of experiment simulations through the 3D Monte-Carlo MCNP transport code.