Abstract
In order to test new EFF-3 evaluations for 9Be, 56Fe, 58Ni and 60Ni, MCNP based analyses of the JAERI/FNS beryllium and iron TOF experiments and the IPPE Obninsk nickel TOF experiment were carried out. The analyses showed the followings results; EFF-3.0 56Fe (the previous version of EFF-3 56Fe) reproduces the measured neutron fluxes best. EFF-3.156Fe (the newest EFF-3 data of 56Fe) tends to overestimate the neutron flux from 5 to 10 MeV by 20 - 30 % and to underestimate it from 0.05 to 0.1 MeV by 20 %. For the newest 9Be, 58Ni and 60Ni EFF-3 data, the achieved accuracy is comparable to FENDL-1 and -2. Monte Carlo sensitivity and uncertainty calculations were also performed with a local version of the MCNP4A code. In general the uncertainties of the neutron flux calculated with EFF-3 data were smaller than those with FENDL-1.
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