Din avgränsning ger 332 träffar.
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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 -
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 -
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 -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...
Innehållstyp: Publikationer -
2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...
Innehållstyp: Publikationer -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Innehållstyp: Publikationer -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Innehållstyp: Publikationer -
2023:06 Instabila matrisdefekter i bestrålat reaktortankstål med höga nickel- och manganhalter
Strålsäkerhetsmyndighetens perspektiv Bakgrund Reaktortankstål påverkas av neutronbestrålning så att omslagstemperaturen, omslag från sprött till segt brott, ökar och att segheten i det sega området minskar med ökad grad av bestrålning. För att kunna prediktera framtida försprödningsgrader har så kallade trendkurvor...
Innehållstyp: Publikationer -
2024:16 Initiering av spänningskorrosion i Alloy 600
ICG-EAC Round Robin...
Innehållstyp: Publikationer