Sök

Visar 3296 sökträffar på ”Radiofrekventa fält i omgivningen”

Sortera på:

Relevans Datum
  • 2018:19 Licensing of safety critical software for nuclear reactors

    1421 kB ... and demonstrations of safety of software based systems; – as guidance for manufacturers and major I&C suppliers on the international market. 10 Document Structure From the outset, attention ... technical reference for future improvements in its own regulatory guidance. * * * 13 I INTRODUCTION All government, – indeed every human benefit and enjoyment, every virtue and every...

    Innehållstyp: Dokument
  • 2019-12 Radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova LR

    focused on developing a consensus on the methodological aspects of safety assessment, especially i) specification of the assessment context, ii) description of the waste disposal system, development ... wastes were only thrown in through the opening without special placement measures. Hence Vault I, II and IV could be filled by about 30 m3 of waste each, while Vault III could be filled up by about...

    Innehållstyp: Dokument
  • 2011:11 Handling Interfaces and Time-varying Properties in Radionuclide Transport Models

    3637 kB ... those of the author/authors and do not necessarily coincide with those of the SSM. SSM 2011:11 i Summary This report documents studies undertaken by Quintessa during 2010 in preparation for the ... 3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 0.1 1 10 100 1000 10000 Pore Velocity (m/y) R e la ti v e I n te rf a c e C o n c e n tr a ti o n Figure 9: Average concentration on the fracture-buffer...

    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
  • 2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle

    radioaktiva avfall som produceras i kärnkraftreaktorerna bygger på ett slutförvar flera hundra meter ner i berggrunden. I detta ska det använda bränslet placeras, inneslutet i kopparkapslar, varpå slutförvaret ... tidsrymd som anläggningen är tänkt att innehålla kärnmaterial samt att det material som är placerat i förvaret kommer att vara mycket svårt att få tillgång till. Slutförvarets otillgänglighet innebär att...

    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
  • 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
  • 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
  • 2010:05 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