Din avgränsning ger 742 träffar.
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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.
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2012:26 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill - Chemical erosion processes
The SR-Site documentation relevant to this review topic was found to be of sufficiently high quality overall to justify further consideration in the Main Review Phase of SSM’s PCS (Post-closure safety) project. Several specific topics for which complementary information and clarifications should be requested from SKB were also identified (Appendix 2). Specific review topics for consideration...
Innehållstyp: Publikationer -
2010:33 Lineament interpretation Short review and methodology
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site that may have potential for hosting a...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2011:03 On Decommissioning Cost for Nuclear Power Plants
This research report summarizes what has changed over the latest 15 years concerning actual and estimated costs for the D&D of nuclear power plants that have been shut down permanently. It also reports on the availability of detailed information for actual nuclear power plant D&D cost breakdowns. The results will be one supporting document in the review of the estimates submitted for...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2015:34 Inventering av oförstörande provningsmetoder för undersökning av infästningar
Bakgrund I de Svenska kärnkraftverken och andra kärntekniska anläggningar finns ett stort antal fästplattor i betong, ingjutna alternativt eftermonterade. Fästplattornas uppgift är att förankra säkerhetsrelaterade system och det är därför av stor vikt att dess integritet är bibehållen under dess livslängd. Fästplattan består...
Innehållstyp: Publikationer -
2015:28 Utvärdering av materialdata för befintliga betongkonstruktioner - med inriktning på verifiering av förankringar vid kärntekniska anläggningar
Bakgrund I de Svenska kärnkraftverken finns ett stort antal fästplattor som är ingjutna alternativt eftermonterade. Fästplattan består av en förankringsplatta med tillhörande betonginfästning. Kapaciteten för flera av de viktigare brottmoderna för betonginfästningar styrs av hållfastheten hos omgivande betong. Betongens hållfasthet...
Innehållstyp: Publikationer