Preliminary Analysis of Radiation Shielding for B-type HIC Transport Package

A radiation shielding analysis has been conducted using a computer program MCNP5 for a B-type HIC (High Integrated Container) Transport Package, which contains HIC with radioactive waste or Spent Resin, for transportation from nuclear power plant sites to disposal repository. Radiation source term is first carefully determined from the safety analysis reports related to HIC for appropriate calculation. And then MCNP (v.5) is performed to obtain the minimum thickness of HIC transport package, which meets the dose rate limit for HIC transport package prescribed in Korea Nuclear Law and IAEA Safety Standards for Radioactive Material Transport. In addition, some other analyses are done about the trend of dose rates depending on the thickness of shielding material and distance from the package