Neutron transport calculations around the reactor pressure vessel by the ACE-FRENDY-CBZ sequence

Chiba, Go*; Tada, Kenichi   ; Yamamoto, Akio*

The one-dimensional spherical multi-group neutron transport calculation was carried to calculate around the reactor pressure vessel by the ACE-FRENDY-CBZ sequence for the quantification of the prediction accuracy of this sequence. The fine energy groups calculation results showed a good agreement with the continuous-energy Monte Carlo code MVP. The calculation results indicate that the prediction accuracy of this method is higher than that of the conventional multi-group calculation method.