Changes in the mechanical properties of reactor vessel materials result from the exposure to the fast neutron. The use of MOX fuel in LWRs presents different neutron characteristics, and it is worthy to study whether the present software can calculate the structural integrity of reactor components. This paper use MCNP, TORT and SCALE to calculate VENUS-2 benchmark, and the calculation shows that all this software can get reasonable result that can be used in the design. MCNP has the highest accuracy.