Din avgränsning ger 301 träffar.
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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 -
2015:24 Dimensionering av nukleära byggnadskonstruktioner (DNB)
Strålsäkerhetsmyndigheten (SSM) och de svenska tillståndshavarna har tidigare i ett samfinansierat forskningsprojekt tagit fram anvisningar för dimensionering av nukleära byggnadskonstruktioner, DNB. Rapporten som är baserad på Eurokoderna publicerades som SSM rapport 2014:06 För att ytterligare förbättra DNB och för att säkerställa...
Innehållstyp: Publikationer -
2015:25 Design Guide for Nuclear Civil Structures (DNB)
The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...
Innehållstyp: Publikationer -
2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion
Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...
Innehållstyp: Publikationer -
2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load
Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...
Innehållstyp: Publikationer -
2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen
One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...
Innehållstyp: Publikationer -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Innehållstyp: Publikationer -
2007:09 DECOVALEX-THMC - Task C
This report describes the results of Task C1 of the international DECOVALEX– THMC project devoted to Excavation Damage Zone (EDZ) in argillaceous rock at the Tournemire site in France. Task C of the project is aimed to understand the physical phenomena induced by excavation in the argillaceous rock. The task is to develop adequate numerical models for interpretation of observed damaged zones...
Innehållstyp: Publikationer -
2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS
Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...
Innehållstyp: Publikationer -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Innehållstyp: Publikationer