Abstract
An evaluation of surface dose rates calculated by MCNP with three different source geometric representations for a waste package containing 21 pressurized water reactor (PWR) spent fuel assemblies is provided. The three geometric representations for the source region consist of a radial homogenization inside the waste package cavity, a homogenization of the assembly contents within the transverse dimensions of the assembly, and a detailed geometric model. Conservative dose rates are predicted by the source homogenized inside the cavity, while the detailed and the homogenized assembly models give comparative results.
| Original language | English |
|---|---|
| Pages (from-to) | 320-323 |
| Number of pages | 4 |
| Journal | Journal of Nuclear Science and Technology |
| Volume | 37 |
| DOIs | |
| State | Published - Mar 2000 |
| Externally published | Yes |
Keywords
- Conservative calculations
- Detailed geometric representation
- Gamma and neutron surface dose rate
- MCNP dose calculations
- Source homogenization
- Waste package