Together with my Dutch partner Nuclear Shields B.V., I have developed transport and storage containers for nuclear waste. These include a heavily shielded container for high-level CSD-V canisters with vitrified reprocessing waste and a versatile container for low- and intermediate-level waste in 200 l drums or as loose waste.
In addition to its excellent mechanical properties in terms of handling and stability and its ability to prevent leakage of liquid waste, the container is also optimized in terms of its radiological properties.
- Different shielding configurations: 0–50 mm lead
- Calculation of the maximum possible 60Co activity regarding dose rate limits according to IAEA/ADR
- For different loading masses to account for self-shielding effects
- Simulation of spatially resolved dose rate for identification and elimination of shielding weaknesses
This type B(U) cask is designed especially for the transport and storage of single high-level CSD-V canisters. The large amount of heat generated by the waste is countered by a sophisticated passive cooling system.
Since the vitrified reprocessing waste consists of high-intensity photon and neutron emitters, a massive two-stage shielding system is used. This shielding system is optimized to ensure compliance to the dose rate limits according to IAEA/ADR even in the case of canisters with the largest possible activity inventory.
- Analysis of the activity inventories of all German CSD-V canisters
- Radiation source for simulations: all relevant photon and neutron emitting nuclides with their maximum occurring activity
- Based on this fictitious “worst case” canister, the neutron absorber made of polyethylene and the photon shielding consisting of lead were optimized in multidimensional parameter studies.