Home / Publications / Journals / Nuclear Technology / Volume 117 / Number 2
Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 184-194
Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35324
Articles are hosted by Taylor and Francis Online.
A typical advanced boiling water reactor (BWR) pin cell configuration is used to develop numerical benchmarks for the effects of moderator and fuel properties on the eigenvalue. Results are developed for pin cell configurations with different moderator densities and temperatures and different fuel exposures and temperatures. These configurations (98) correspond to those typical of cold, hot-operating, and transient conditions in B WRs. All of the calculations were performed using the Monte Carlo code MCNP with the continuous-energy cross sections derived from version VI of the Evaluated Nuclear Data Files ENDF/B.