Category of Content

Siting Experience Documents Only

Publication Date

Country

Keywords

Displaying 1 - 8 of 8

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

Implementation of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth National Report of Switzerland

SED Publication Type

Implementation of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth National Report of Switzerland

Author
Federal Department for the Environment, Transport, Energy and Communications DETEC
Publication Date

Historically, electricity generated in Switzerland came exclusively from hydropower without any recourse to fossil fuels, the latter not being available as a natural resource in the country. In the mid 1950's, an interest in the relatively new nuclear energy technology was manifested to cover an increasing electricity demand. In accordance with the general policy concerning the production of electricity, the promotion and use of nuclear energy was left to the initiative of the private sector.

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

Identifying remaining socio-technical challenges at the national level: Switzerland

SED Publication Type

Identifying remaining socio-technical challenges at the national level: Switzerland

Author
Anne Minhans ,
Beate Kallenbach-Herbert
Publication Date

This report was written within the EU-project InSOTEC (www.insotec.eu) which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. In a first step 13 countries have been analysed in order to identify prevailing socio-technical challenges.

repository waste management siting switzerland wp 1 ms 7
Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: