Visar 3296 sökträffar på ”Radiofrekventa fält i omgivningen”
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2005:20 Expert Panel Elicitation of Seismicity Following Glaciation in Sweden
3126 ... Hora and Mikael Jensen SSI Rapport 2005:20 Rapport från Statens strålskyddsinstitut tillgänglig i sin helhet via www.ssi.se 5LTRAVIOLETSOLARANDOPTICALRADIATION 5LTRAVIOLETRADIATIONFROMT ... Seismicity Following Glaciation in Swe- den / Formella Expertbedömningar av Jordskalv efter Nedisning i Sverige. Summary: The Swedish Radiation Protection Authority, the Swedish Nuclear Power Inspectorate...
Innehållstyp: Dokument -
98:25 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods
Development Program in Diagnostics and Monitoring with Neutron Noise Methods Stage 4. Final report I. Pázsit and J. K-H. Karlsson Department of Reactor Physics Chalmers University of Technology Göteborg ... of the rod (which in norm culated and discussed. E used. Actually this pertu ever, this point source i this fact makes the prob f models for the calculation of neutron noise nd model studies of neutron...
Innehållstyp: Dokument -
2004:29 Stress Corrosion Cracking Testing of Non-Sensitised Stainless Steel
av interkristallin spänningskorrosion (IGSCC) har påträffats i icke-sensibiliserat rostfritt stål i kärnkraftverk i Sverige och utomlands. I denna undersökning har inverkan av kallbearbetningsgrad och ... med undersökningen har varit att belysa dessa provningsmetoders användbarhet för att studera IGSCC i icke-sensibiliserat rostfritt stål. IGSCC erhölls vid CBB-provningar. Flertalet sprickor började...
Innehållstyp: Dokument -
2005:07 An Assessment of SKB's Performance Assessment Calculations in the Interim Main Report for the Safety Assessment SR-Can (pdf 513 kB)
513 kB ... compartments. For diffusion in a given direction, the resistance between compartments i and j is given by: )( 2 1 jj j ii i ij AD d AD d +=Ω , 5.1 where A is the area perpendicular to the direction ... associated transfer rate between compartment i and compartment j is ijλ given by: iji ij Ω= κλ 1 , 5.2 where iκ is the capacity of compartment i defined by: iiii VRθκ = , 5.3 where...
Innehållstyp: Dokument -
2019:02 Research within technical safeguard at Chalmers University of Technology during 2016-2017
personnel during 2016-06-30 – 2017-12-31 with a research grant, Dnr SSM2016-662 from SSM, with undersigned (I.P.) as the project leader. The research was concentrated on two main subjects: Developing a method for ... personnel during 2016-06-30 – 2017-12-31 with a research grant, Dnr SSM2016-662 from SSM, with undersigned (I.P.) as the project leader. The research was concentrated on two main subjects: Developing a method for...
Innehållstyp: Publikationer -
2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
shell. The copper shell is not in itself load carrying but must retain its corrosion barrier ability (i.e thickness) when the compressive load is applied very slowly. For materials where the load is applied ... shell. The copper shell is not in itself load carrying but must retain its corrosion barrier ability (i.e thickness) when the compressive load is applied very slowly. For materials where the load is applied...
Innehållstyp: Publikationer -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
are also available for evaluating SCC susceptibility like constant strain or constant load testing. I this study only the first testing method, SSRT, has been employed to study SCC susceptibility of oxygen ... are also available for evaluating SCC susceptibility like constant strain or constant load testing. I this study only the first testing method, SSRT, has been employed to study SCC susceptibility of oxygen...
Innehållstyp: Publikationer -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
and data sources are summarized in this section. We considered 22 radionuclides (C-14, Cs-135, I-129, Nb-94, Ni-59, Np-237, Pb-210, Pu-238, Pu-239, Pu-240, Pu-242, Ra-226, Rn-222, Se-79, Tc-99, Th-230 ... derives from the decay of the Pu-241 and Am-241 parents. A fraction of the inventory of C-14, Cs-135, I-129, Se-79, Tc-99, Ni-59, and Nb-94 was assumed to be released into the in-canister water immediately...
Innehållstyp: Dokument -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
• förslag på generella principer för att på optimalt sätt hantera utmaningar för integriteten, i synnerhet vad gäller åldrande av betongstrukturer. Syfte Syftet med forskningsprojektet är att skapa ... gällande hantering av åldersrelaterade betongdegraderingar vid kärntekniska anläggningar. Varje deltagare i ASCET-projektet bidrog med en skriftlig rapport om sin forskningsverksamhet gällande betongde- gradering...
Innehållstyp: Dokument -
2014:11 Technical Note, Radionuclide Solubility Limits in SKB’s Safety Case
kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta information i avgränsade frågor. I SSM:s Technical note-serie rapporteras resultaten från ... uppdrag är att utvärdera SKB:s metod för beräkning av löslighetsgränser genom ytterligare granskning i förhållande det arbete som gjordes under den initiala granskningsfasen samt genom att repro- ducera...
Innehållstyp: Dokument