Research Article

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

Table 3

MCNP simulation results.

Concrete  
thickness (cm)
Dose per decay at the source (pSv)Relative Error

105.36E-080.0109
202.18E-100.0495
306.36E-130.0712
401.86E-160.1721
501.90E-190.1095