Din avgränsning ger 996 träffar.
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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 ... 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 Facility...
Innehållstyp: Publikationer -
2003:19 Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC
Henri Condé, Waclaw Gudowski, Jan Blomgren, Jan-Olov Liljenzin, Nils Olsson, Curt Mileikovsky, Jan Wallenius. March 2003 SKI English...
Innehållstyp: Publikationer -
99:11 Spatial Variability of Geosphere Parameters and the Impact of the F-ratio on Radionuclide Release
António Pereira SKI English...
Innehållstyp: Publikationer -
2012:71 Identification of Brittle Deformation Zones and Weakness Zones
Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which ... concepts of “respect distances” and “full perimeter intersection criteria” developed by SKB are based on the understanding of fracture extension and the definition of deformation zones. A common methodology...
Innehållstyp: Publikationer -
2014:05 Technical Note, Assessment of flows to deposition holes – Main Review Phase
SKB’s conceptual model for flow through the fractured rock at Forsmark is based on a division between highly fractured deformation zones (described in terms of deterministic geometry), and the more sparsely ... these assumptions on flows to deposition holes is judged to be minor, compared with uncertainties in the model for the more sparsely fractured rock. This assessment focuses mainly on the statistical model...
Innehållstyp: Publikationer -
2010:29 SKI:s och SSI:s synpunkter på SKB:s FoU/Fud-program 1986-2007
frågeställningar i samband med granskningarna. Myndigheternas målsättning har varit att påverka SKB:s utformning av Fud-programmen, bland annat med syfte att framtida slutförvarsansökningar ska kunna uppfylla ... kärnbränsle första kvartalet 2011 och därför är det nu angeläget för Strålsäkerhetsmyndigheten (SSM) att följa upp SKB:s hantering av viktiga synpunkter på Fud-programmen. En utgångspunkt för denna uppföljning...
Innehållstyp: Publikationer -
2014:59 Technical Note, Relation between earthquake magnitude, fracture length and fracture shear displacement in the KBS-3 repository at Forsmark – Main Review Phase
spent nuclear fuel at the Forsmark site. Two sources of threat are: i) events due to thermal loading on the rock mass by the heat from canisters with spent nuclear fuel, and ii) seismic events, i.e. earthquakes ... the shear displacement on rock fractures induced either by the eff ect of thermal loading, or by an earthquake at a nearby deformation zone, or by the combination of the two. In SKB’s safety assessment SR-Site...
Innehållstyp: Publikationer -
2003:43 Development of an Estimating Procedure for the Annual PLAN Process - with Special Emphasis on the Estimating Group
Steen Lichtenberg SKI English...
Innehållstyp: Publikationer -
99:44 The Effects of Impurities on the Properties of OFP Copper Specified for the Copper Iron Canister
W H Bowyer SKI English...
Innehållstyp: Publikationer -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although there is no direct evidence from the field of stress corrosion cracking risks in reactor pressure vessels, the effect of chloride excursions on stress corrosion cracking crack growth in reactor ... Although there is no direct evidence from the field of stress corrosion cracking risks in reactor pressure vessels, the effect of chloride excursions on stress corrosion cracking crack growth in reactor...
Innehållstyp: Publikationer