Filtered generated 276 hits.
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1993:11 Methods for determination of strontium -90 in food and environmental samples by Cerenkov counting
The procedure for determination of strontuim-90 (=yttrium-90) by HDEHPextraction of yttrium-90 and counting the Cerenkov radiation in a liquid scintillation counter, is applicable for all kind of samples. Prior to analyses liquid samples are evaporated to dryness and ashed. Environmental and food samples are oven dried and ashed. The ash is dissolved in 1 molar hydrochloric acid and, at pH...
Content type: Publications -
2017:27e Review of Swedish emergency planning zones and distances
ESS research facility Summary On 22 October 2015, the Government of Sweden commissioned the Swedish Radiation Safety Authority (SSM) to, in consultation with the Swedish Civil Contingencies Agency (MSB), relevant county administrative boards and the other authorities and stakeholders concerned, perform a review of emergency planning zones and emergency planning distances applying to...
Content type: Publications -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Content type: Publications -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Content type: Publications -
2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?
The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...
Content type: Publications -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...
Content type: Publications -
2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review
Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...
Content type: Publications -
2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites
An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...
Content type: Publications -
2010:31 Buffer erosion: An overview of concepts and potential safety consequences
In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...
Content type: Publications -
2008:57 Discrete Feature Model (DFM) User Documentation
This manual describes the DiscreteFeature Model (DFM) software package for modelling groundwater flow and solute transport in networks of discrete features. A discretefeature conceptual model represents fractures and other waterconducting features around a repository as discrete conductors surrounded by a rock matrix which is usually treated as impermeable. This approximation may be valid for...
Content type: Publications