A typical advanced boiling water reactor (BWR) pin cell configuration
is used to develop numerical benchmarks for the effects of moderator a
nd fuel properties on the eigenvalue. Results ape developed for pin ce
ll configurations with different moderator densities and temperatures
and different fuel exposures and temperatures. These configurations (9
8) correspond to those typical of cold, hot-operating, and transient c
onditions in BWRs. All of the calculations were performed using the Mo
nte Carte code MCNP with the continuous-energy cross sections derived
from version VI of the Evaluated Nuclear Data Files ENDF/B.