Filtered generated 45 hits.
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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 -
2012:32 Technical Note, Groundwater Chemistry in SKB’s Safety Assessment SR-Site: Initial Review
This preliminary review of SR-Site is focused specifically on the treatment of groundwater chemistry in the description of the Forsmark site and in the long-term safety of a deep geological repository at Forsmark. Data for the chemical and isotopic compositions of groundwaters have contributed to a site descriptive model (SDM) for Forsmark. In that SDM, groundwater chemistry is interpreted...
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 -
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 -
2012:48 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 -
2012:29 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
De dokument i SR-Site som är relevanta till detta granskningsområde bedöms vara generellt i tillräckligt hög kvalitet för att utgöra underlagsmaterial för vidare granskning i huvudgranskningsfasen av SSM:s GLS- (granskning av långsiktig säkerhet) projekt. Behov av kompletterande information eller förtydliganden har dock identifierats inom...
Content type: Publications -
2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper
The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...
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 -
2012:13 Technical Note, A review of the creep ductility of copper for nuclear waste canister application
SKB has presented insufficient evidence to justify their position that the OFP copper has an adequate creep ductility during long term storage. Their large body of experiments only serves to prove that the creep ductility is sufficient for much shorter time spans than the intended storage times. There is a clear need for a credible theory of creep brittleness of OFP copper which will permit...
Content type: Publications -
2012:06 Decommissioning Cost Assessment
The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in...
Content type: Publications