Filtered generated 230 hits.
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2003:19 Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC
Henri Condé, Waclaw Gudowski, Jan Blomgren, Jan-Olov Liljenzin, Nils Olsson, Curt Mileikovsky, Jan Wallenius. March 2003 SKI English...
Content type: Publications -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Content type: Publications -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Content type: Publications -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Content type: Publications -
2012:53 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site – Initial Review Phase
SRK Consulting (UK) Limited (SRK) has reviewed the Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site in Sweden. The review assignment is part of a Swedish Radiation Safety Authority (SSM) Initial Review Phase. The review was carried out by David Saiang (PhD) on behalf of SRK. Therefore some of the views expressed in the...
Content type: Publications -
2012:43 Technical Note, Literature review of groundwater flow in permafrost
The Swedish Radiation Safety Authority (SSM) assigned the task of compiling the state of the knowledge with respect to groundwater flow in permafrost conditions. In particular, the study was to consider whether (i) the main processes related to groundwater flow in permafrost were understood, (ii) appropriate field data was available, and (iii) current models appropriately represent the...
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 -
2013:35 Technical Note, Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of a damage zone around the excavations – Main Review Phase
This assignment, performed at Southwest Research Institute, focusses on evaluating SKB’s assessment of potential occurrence of damaged rock zones (also referred to as excavation-damaged zone or EDZ) around underground excavations at the site. This report presents the authors’ evaluation of SKB’s assessment in the specific area based on questions raised by SSM. The evaluation includes...
Content type: Publications -
2012:24 Technical Note, Initial Review of SR-Site Main Report
The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a repository for the final disposal of spent nuclear fuel. SKB’s Application includes an assessment of the long-term safety of the proposed repository. The assessment is known as SR-Site. This technical note records the findings from a...
Content type: Publications -
2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment
In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.
Content type: Publications