Filtered generated 146 hits.
-
2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity
Main Review Phase Introduction The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain...
Content type: Publications -
2015:53 Ductile tearing – Micromechanical analyses and experimental study
In this report, the project "Ductile Tearing-Micromechanical analyses and experimental study" is presented. In the project, numerical cell modeling has been conducted using the shear modified Gurson model proposed by Nahshon and Hutchinson to evaluate its capability in predicting the effect of residual stresses. Experimental work has also been conducted for material characterization.
Content type: Publications -
2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”
The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review SKB’s presentation on possible influence from stray currents from high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English The general objective of...
Content type: Publications -
2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology
Initial review phase SSM English Initial review phase...
Content type: Publications -
2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus
Kjell Pettersson SSM English...
Content type: Publications -
2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes
The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...
Content type: Publications -
2015:48 Technical Note, Supplementary review of SKB’s further RFI response
Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...
Content type: Publications -
2015:08 Technical Note, Rheological properties of the Bentonite Buffer
Rheological properties for bentonite at high densities The properties of bentonite at high densities are extremely important and it appears as it has been to a certain extent well researched and understood, although further investigations regarding swelling of the bentonite would be welcome. What, however, seems to be missing is a comprehensive constitutive model capturing all the different...
Content type: Publications -
2015:22 Technical Note, Further modelling and sensitivity study using the GEMA-Site “alternative biosphere models” and review of material from SKB’s RFI response
Denna rapport har upprättats som en del av SSM:s huvudgranskning av SKB:s säkerhetsanalys av den långsiktiga säkerheten för KBS-3 (SR-Site), en geologisk slutförvarsanläggning, som SKB planerar uppföra i Forsmark. Granskningen tar upp de metoder som används för dosberäkningar i SR-Site, speciellt vad gäller transporter, ackumulering och...
Content type: Publications -
2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel
The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.
Content type: Publications