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Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Author(s)
OCRWM
Publication Date
The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation.
high level waste radiation protection storage hanford site 2-mco/2-dhlw dose calculation multi-canister overpack defense

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Author(s)
Sandia National Laboratories
Publication Date

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.

yucca mountain radionuclides dose calculation isotopic concentrations engineered barrier system geochemical analysis

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Author(s)
Sandia National Laboratories
Publication Date

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.

yucca mountain radiochemical analysis storage radionuclides dose calculation isotopic concentrations

Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences

Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences

Author(s)
Georgeta Radulescu
Publication Date

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.

high level waste spent fuel yucca mountain dose calculation naval spent nuclear fuel used fuel

National Report of Poland on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Polish 3rd National Report as Referred to in Article 32 of the Joint Convention

SED Publication Type

National Report of Poland on Compliance with the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Polish 3rd National Report as Referred to in Article 32 of the Joint Convention

Author
Polish National Atomic Energy Agency
Publication Date

This Report has been prepared, according to the guidelines established by the Contracting Parties under Article 29.2(iii), to fulfil the obligations of the Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, signed by Poland on 30 September 1997 in Vienna, and ratified by the President of the Republic of Poland on 9 March 2000. The corresponding instruments of ratification were deposited with the IAEA on 5 May 2000. The Convention entered into force on 18 June 2001.

siting national report joint convention spent fuel management poland radioactive waste management
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