Filtered generated 377 hits.
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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 -
2012:46 Technical Note, Review of Landscape Models used in SR-Site
As part of SSM’s Initial Review phase of SKB’s SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site, Quintessa was given the assignment to consider whether the landscape models and supporting data utilised by SKB are appropriate and fit for purpose. This Technical Note summarises the findings of Quintessa’s review. SKB’s approach to the...
Content type: Publications -
2012:42 Technical Note, Initial review of physical properties and processes of the buffer and backfill – Installation and initial state
The technical note briefly summarises the proposed designs and functions of the buffer and backfill, and examines SKB’s progress in manufacturing, installing and testing its proposed solutions. In brief, the review suggests that there are some procedural and practical engineering aspects (e.g., quality assurance procedures, backfilling rates) and several physical processes to do with the...
Content type: Publications -
2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU
– consequence analysis and hydrogeological aspects Main review phase...
Content type: Publications -
2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study
SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...
Content type: Publications -
2019:01 Research within technical safeguard at Uppsala university during 2016-20
Summary Uppsala University has since January 2016 undertaken an extensive research programme in technical nuclear safeguards within the framework of contract SSM2016-661, including in total 3 PhD students and 7 senior researchers. This report marks the final reporting covered by this contract. The executed research covers the following projects; (1) Methodologies for safeguards assessment of...
Content type: Publications -
2012:35 Technical Note, Review of SKB’s Code Documentation and QA for the SR-Site Safety Assessment
This initial review examined the Swedish Nuclear Fuel and Waste Management Company (SKB) code documentation and quality assurance, which is important to the safety assessment SR-Site because the computer codes used must be both suitable for the analyses performed and capable of producing accurate results for those analyses. SKB has prepared a report that summarizes the code documentation...
Content type: Publications -
2018:19 Licensing of safety critical software for nuclear reactors
Background This report is the 7th revision of the report. The task force was formed in 1994 as a group of experts on safety critical software. The members come from regulatory authorities and/or their technical support organization. The report, without the SSM cover and this page, will be published by or available at the websites of the other participating organizations. Effect on SSM...
Content type: Publications -
2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth
The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.
Content type: Publications -
2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues
The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...
Content type: Publications