The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.

Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.