Din avgränsning ger 199 träffar.
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2019:06 The Changing Landscape of Non-proliferation and the EU
........................................................................................ 3 Paper I: Safeguards and the Role of the Member State .......................................... 4 1. Introduction ... på de nationella myndigheterna under de olika systemen? Hur har de nationella myndigheternas roll i medlemsstaterna förändrats över tid? Den andra delen belyser kopplingen mellan nukleär icke-spridning...
Innehållstyp: Dokument -
2019:08 Recent Research on EMF and Health Risk, Thirteenth report from SSM’s Scientific Council on Electromagnetic Fields, 2018
explore if these associations are true or if alternative explanations such as residual confounding, i.e. other factors related to MRI work and the outcomes under investigations, underlie the observed associations ... explore if these associations are true or if alternative explanations such as residual confounding, i.e. other factors related to MRI work and the outcomes under investigations, underlie the observed associations...
Innehållstyp: Publikationer -
00:48 The Use of Risk Based Methods for Establishing ISI-Priorities for Piping Components at Oskarshamn 1 Nuclear Power Station
They are classified with respect to similar consequences for core damage. For the initiating events, i e the LOCA frequencies, the WASH-1400 study [13] has been used in the PSA for O1. The WASH-1400 study ... CORE DAMAGE In this study, the following equation is used for evaluating the Risk for Core Damage, i e the Core Damage Frequency CDF: CDF P(small leak) C(small leak) + P(large leak) C(large leak) +...
Innehållstyp: Dokument -
2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU
47E+08 4.39E+07 1.04E+08 Cs-135 1.44E+06 1.10E+07 9.17E+04 5.29E+07 6.88E+08 8.67E+07 6.92E+05 I-129 3.53E+05 3.26E+06 2.75E+04 8.48E+06 9.72E+07 3.62E+07 6.53E+05 Mo-93 1.37E+07 6.49E+07 9.61E+03 ... higher peak fluxes of radionuclides that are not sorbed, or are only weakly sorbed, e.g. C-14_org and I-129, and more rapid decrease in the fluxes beyond the peak. In the CCL_BC, concrete is assumed...
Innehållstyp: Dokument -
2019:20 Assessment of structures subject to concrete pathologies (ASCET), phase 3
(normala) betongkonstruktioner som utsätts för cyklisk skjuvande belastning och svarar med olinjär respons i materialet. Detta för att kunna tillgodose de behov svensk myndighet och anläggningsägare kan komma ... presenteras i den här rapporten utvecklades inför den andra fasen av ASCET [2]. En brist som identifierats med modellen är att armeringen var stelt kopplad till betongen. SCTE:s medverkan i den tredje fasen...
Innehållstyp: Dokument -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
Equation (4-4) where, rf is the repository fracture radius and sjA(i) is the area of the i-th smooth joint. Figure 4-6. Disk fracture (side view: a, front view: c) and representation ... stress model. Table 4-7 lists the magnitudes of each in- situ stress components of the stress models: (i) S1: Present day most likely stress model (Martin 2007); (ii) S2: Glacially induced stress model in...
Innehållstyp: Dokument -
Appendix 4 The fuel fabrication plant in Västerås
4E+13 Halogens I-131 8.02 d 3.2E+11 3.2E+10 2.9E+11 I-132 2.30 h 3.9E+13 3.9E+12 3.5E+13 I-133 20.8 h 5.9E+12 5.9E+11 5.3E+12 I-134 52.5 min. 1.5E+14 1.5E+13 1.3E+14 I-135 6.57 h 1.7E+13 ... outcomes for ground deposition of iodine (I-131) and strontium (Sr-89 and Sr-90) are shown in Figure 8 and Figure 9. The intervention level for ground deposition of I-131, at 5 kBq/m2, may be exceeded out...
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 -
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 -
2019:22 Technical Note, SSM’s external experts’ reviews of SKB’s report on supplementary information on canister integrity issues
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 ... SSM:s egen granskning av korrosionsfrågor, korrosionsfrågornas betydelse för kapselns integritet i slutförvarsmiljön, samt konsekvensberäkningar kopplade till dessa frågeställningar. Innehållsförteckning...
Innehållstyp: Dokument
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