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Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
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.
Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
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.
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay
There are no nuclear power stations and no nuclear fuel cycle activities in Uruguay. There are only disused radioactive sources from medical and industrial practices and there is a disused conditioned neutron Pu-239 source with 185 TBq, waiting for its reshipment to the United States. This material is stored in the building in which it was an old research reactor. The application of the Convention is limited to radioactive waste arising from the medical, industrial and research applications of radioisotopes.