Analysis of fast reactor shielding benchmarks

We present in this paper our analyses of three bench mark problems on neutron transport in sodium, iron-sodium layers and graphite. The studies were carried out to assess our computational facilities for taking up bulk shield calculations for the large fast reactor which is under design at our center. Monte Carlo and one dimensional discrete ordinate methods with 100 group DLC-2 cross sections based on ENDF/B were used in these analyses. We find that our calculations compare well with the benchmark results (author)