Din avgränsning ger 751 träffar.
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2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Innehållstyp: Publikationer -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Innehållstyp: Publikationer -
2007:08 DECOVALEX-THMC - Task B
This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...
Innehållstyp: Publikationer -
2007:11 Review of Quality Assurance in SKBs Repository Research Experiments
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...
Innehållstyp: Publikationer -
2007:30 Modelling the Interaction of Low pH Cements and Bentonite
Concrete and cement are used in constructions as well as in conditioning of waste inrepositories for radioactive waste. It is well known that in the hyperalkaline conditions (pH > 12) of standard cement pore fluids, there is potential for deleterious effects upon the host rock and other EBS materials, notably bentonite, in geological repositories. Low pH cements are beginning to be considered...
Innehållstyp: Publikationer -
2014:54 Technical Note, Further Modelling Comparison of Simple Reference Biosphere Models with the LDF Modelling Approach – Main Review Phase
This Technical Note describes further use of simple reference biosphere models for SSM’s review of the Landscape Dose Factor (LDF) approach adopted by SKB in the SR‑Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. Simple biosphere models for the Forsmark site under temperate climate conditions were previously developed for SSM’s review and are...
Innehållstyp: Publikationer -
2014:58 Technical Note, Rock Mechanics - Assessing probability and extent of blind faults and fault-end growth around the KBS-3 repository at Forsmark – Main Review Phase
To get a general understanding of the stability conditions of the fault and deformation zone inventory at Forsmark a reactivation potential analysis was carried out. At present-day stress conditions the deformation zones are stable and show no large deformations or detected seismicity. Any changes in stress, and in particular increase of differential stress on deformation zones, might cause...
Innehållstyp: Publikationer -
2014:47 Technical Note, Assessment of groundwater salinity evolution at repository depth and especially the impact of dilute water infiltration
Groundwater compositions entering deposition holes in the repository will be progressively diluted over time because of expected changes of topographic and climatic conditions at Forsmark. This is a long-term safety issue because very dilute water could destabilise compacted bentonite and erode buffer, leading to advective movement of sulphide-containing water to the canister surface. SKB’s...
Innehållstyp: Publikationer -
2014:55 Technical Note, Further Reproduction of SKB’s Calculation Cases and Independent
Som en del av säkerhetsanalysen SR-Site presenterar SKB modellresultat som illustrerar kapseln och buffertens säkerhetsfunktioner. I var och en av de fem beräkningsfallen är delar av kapsel och/eller buffert frånvarande i modellen av slutförvarssystemet. Modellresultaten jämförs inte med säkerhetskriterier eftersom beräkningsfallen innehåller...
Innehållstyp: Publikationer -
2015:29 Technical Note, Quality Assurance in SKB’s Copper Corrosion Experiments
I Sverige planeras slutförvaring av använt kärnbränsle. Metoden som har utvecklats kallas för KBS-3 och den bygger på tre skyddsbarriärer; kopparkapslar, bentonitlera och det svenska urberget. Det specifika syftet med den här rapporten är att få en förståelse för, och en bedömning av, SKB:s kvalitetssäkring av deras försök...
Innehållstyp: Publikationer