Published June 2011 | Version v1
Journal article

Simulation and analysis the neutron dose distribution of KBS-3 spent nuclear fuel canister by MCNP

  • 1. School of Nuclear Engineering and Technology, East China Institute of Technology, Fuzhou (China)
  • 2. Key Laboratory of Radioactive Geology and Exploration Technology Fundamental Science for National Defense, East China Institute of Technology, Fuzhou (China)

Description

The KBS-3 canister for geological disposal of spent nuclear fuel in Sweden consists of a ductile cast iron insert and a copper shielding. The ductile cast iron insert provides the mechanical strength whereas the copper protects the canister from corrosion. The canister inserts material were referred to as I24, I25 and I26, Spent nuclear fuel make the repository in high radiant intensity. The radiation analysis of canister insert is important in canister transport, the dose analysis of repository and groundwater radiolysis. Groundwater radiolysis, which produces oxidants (H2O2 and O2), will break the deep repository for spent nuclear fuel. The neutron dose distribution of canister surface with different kinds of canister inserts (I24, I25 and I26) is calculated by MCNP. Analysing the calculation results, we offer a reference for selecting canister inserts material. (authors)

Additional details

Publishing Information

Journal Title
Journal of East China Institute of Technology. Natural Science
Journal Volume
34
Journal Issue
2
Journal Page Range
p. 160-164
ISSN
1674-3504

Optional Information

Notes
8 figs., 1 tabs., 6 refs.