Din avgränsning ger 2178 träffar.
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2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark
3825 kB ... of α was adjusted manually to approximately minimize the squared residuals: i ii xhPxP=r 2 01 2 where: xi = position of the centre of the ith borehole interval (of 1 ... i iendiplugiusable lll=L where: li = length of the ith deposition tunnel lplug(i) = length reserved for a plug at the entrance to the ith deposition tunnel lend(i) = Minimum...
Innehållstyp: Dokument -
Pronouncement concerning licence application under the Act on Nuclear Activities for proposed expanded operations at SFR.pdf
pointed out by the Authority in the attached review report (Appendix 1). The review report (Part I, section 3.4.4) describes technical issues which SSM considers should be particularly taken into ... closure. For a more detailed line of reasoning relating to the reference design, see Appendix 1, Part I, section 3.1. In the context of the pre-existing facility, SSM exercises regulatory supervision...
Innehållstyp: Dokument -
2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can
SR-Can Budhi Sagar et. al SSI Rapport 2008:05 Rapport från Statens strålskyddsinstitut tillgänglig i sin helhet via www.ssi.se SKI Rapport 2008:15 Ultraviolet, solar and optical radiation Ultraviolet ... do not necessarily coincide with those of the SSI. Författarna svarar själva för innehållet i rapporten. edItorS / redaktörer : Budhi Sagar1, Michael Egan2, Klaus-Jürgen Röhlig3, Neil Chapman4...
Innehållstyp: Dokument -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
5319 kB ... deposition-tunnel utilization factor is calculated as: i iusable, spacingaccept L lN =ε where Naccept is the number of accepted positions and Lusable,i is the "usable" length of the ith deposition tunnel ... segments τi : i iTiτ i iw r τb Δt= τv Δlτa=F 2 iτ r Δl=L iτ r Δt=t iτ iTiτ iwa τb Δl=Δlτa=I 2 iτ iTb Δlτb=I iτ ic ΔlτT=I SSM 2010:05 15...
Innehållstyp: Dokument -
01:44 Recharge-area Nuclear Waste Repository in Southeastern Sweden (pdf 1,58 Mb)
Repository in Southeastern Sweden Demonstration of Hydrogeologic Siting Concepts and Techniques Clifford I. Voss Alden M. Provost November 2001 ISSN 1104-1374 ISRN SKI-R--01/44--SE Research SKI perspective ... : 14.9-000152/00034 and 14.9-000152/01267 SKI-perspektiv Bakgrund och syfte En viktig fråga i valet av slutförvarsplats är betydelsen av in- respektive utströmnings- områden och inlands- respektive...
Innehållstyp: Dokument -
2006:10 Models for MOX fuel behaviour - A selective review
utvärderas och jämförs med UO2. Förekomsten av plutoniumrika områden (agglomerat) i MOX bränsle spär på komplexiteten i bränslebeteendet på detaljnivå. Vi granskar också de senaste erfarenheterna från ... av mikrostrukturen under bestrålning. Resultaten från vår undersökning indikerar att MOX bränsle i allmänhet har högre fissionsgasafrigörelse och heliumavgivning än UO2 bränsle. Denna ökning till en...
Innehållstyp: Dokument -
2010:08 Development of COLLAGE 3
3851 kB ... COLLAGE 2 plus are also known to be important. This report has been produced with the aims of i. assessing how the COLLAGE 2 conceptual model could in- corporate the newly identified FEPs, ii. ... of the porous medium. The two alternative expressions for straining rate in a porous medium are: (i) from Xu et al. (2006): SC k t Sρ o b exp (2.8) in which ok and...
Innehållstyp: Dokument -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
709 ... 5 Concluding remarks 27 References 30 Appendix A Input parameters for cladding models 31 I SSM 2014:18 SSM 2014:18 Abstract The Halden reactor fuel rod loss-of-coolant accident (LOCA) ... results of our computer calculations are compared with measured data for the following parameters: (i) Cladding temperature as a function of time; (ii) Cladding diameter at rupture versus axial position...
Innehållstyp: Dokument -
2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
affected the parameters in Table 2. The results are expressed in terms of the parameter A in Eq. (2), i. e. the parameter that primarily controls the low-cycle fatigue life. The condition set up for the ... surface initial crack nucleate and propagate in the maximum shear direction. During this stage, stage I, the cracks interact strongly with the microstructure of the material. The cracks are called micro-structurally...
Innehållstyp: Dokument -
01:48 Effects of Time Pressure and Noise on Non-Destructive Testing
kritiska för säkerheten och/eller tillgängligheten för kärnkraftverken. Stora variationer i provares förmåga har visats i studier, ofta har trötthet nämnts som delorsak. Inga konkreta resultat har dock presenterats ... prestationen är som högst. För enkla uppgifter ligger detta optimum högre än för mer komplexa uppgifter. I föreliggande studie genomförde tjugo provare manuell ultraljudsprovning av sex testblock med tillverkade...
Innehållstyp: Dokument