Analysis of neutron benchmark experiments to evaluate the JENDL-3 by the continuous energy Monte Carlo Code

The pointwise cross sections on which the JENDL-3 nuclear data library was based were prepared by using the NJOY-83 and the MACROS code system to analyze neutron shielding experiment by the continuous energy Monte Carlo Code MCNP. To evaluate the iron cross sections in the JENDL-3, the ORNL and the WINFRITH iron neutron shielding benchmark experiments were selected to the present purpose. Those two benchmark experiments have not only the reaction rates or the detector responses but also the neutron energy spectra covering a wide energy region. The Monte Carlo MCNP calculations were carried out with the pointwise cross sections from the ENDF/B-IV as well as the JENDL-3. The reliability of the iron cross sections in the JENDL-3 were evaluated through the comparisons and the discussions of the calculated results with experiments. (author)