A core analysis system has been developed for the recent advanced desi
gns of boiling water reactors. This system consists of a fuel assembly
analysis code VMONT and a three-dimensional core simulator COSNEX. To
cope with heterogeneous structures found in the recent high-performan
ce fuel, VMONT employs a Monte Carlo neutron transport calculation met
hod. COSNEX is based on a three-group nodal expansion method to treat
spectral interactions among fuel assemblies. Both codes are vectorized
to meet timing requirements as design tools. The analysis system is v
erified by the tracking of recent plant operations. Although the analy
zed cores are highly heterogeneous in the multienrichment configuratio
n, the system gives sufficient accuracy both in critical eigenvalues a
nd thermal power distributions.