Background: VisualBUS4.2 is an integrated multi-functional neutronics analysis software system improved by FDS (Fission/Fusion Design Study) Team using Monte Carlo method. It is developed to be used in reactor design

critical analysis

shielding and burn-up analysis. Purpose: The purpose of this work is to test the availability of VisualBUS4.2 in complex reactor design. Methods: The IAEA (International Atomic Energy Agency) fast reactor benchmark BN-600 was applied to VisualBUS4.2

and then the resulting neutronic parameters

including effective multiplication factor (keff)

fuel Doppler coefficients (kDfuel)

density coefficients (Wabs

WNa)

axial expansion coefficients (Rax)

radial expansion coefficients (Rrad)

and effective delayed neutron fractions (?eff)

were compared with the results obtained by other affiliations using their programs and databases. Results: keff

kDfuel

Rax

Rrad and ?eff are all matched well with the average value of other affiliations’ results. However

Wabs and WNa were differentiated among all affiliations’ simulation results which require further study. Conclusion: Preliminary test results show VisualBUS4.2 is applicable and reliable in complex reactor design. Abstract