Din avgränsning ger 2180 träffar.
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General data in accordance with the requirements in article 37 of the Euratom Tr 890839_33_1.pdf
Oskarshamn 1 Co-60 2.3E+07 2.0E+07 2.0E+07 I-131 3.1E+07 1.0E+07 - Noble gases 7.6E+13 - - Xe-135 1.7E+13 8.0E+11 - Oskarshamn 2 Co-60 5.0E+07 2.0E+07 2.0E+07 I-131 3.4E+07 1.0E+07 - Noble gases 4.9E+13 ... Co-60 2.0E+07 2.0E+07 2.0E+07 I-131 1.4E+06 1.0E+07 - Noble gases 2.0E+11 - - Xe-135 2.0E+11 8.0E+11 - Oskarshamn 2 Aerosols 1.0E+08 - - Co-60 2.0E+07 2.0E+07 2.0E+07 I-131 9.1E+06 1.0E+07 - Noble...
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Appendix 3 – Dispersion and Dose Calculations
1382 kB ... Cerium (Ce) M Rhodium (Rh) M Cobalt (Co) M Ruthenium (Ru) M Caesium (Cs) F Antimony (Sb) M Iodine (I) (aerosol) F Selenium (Se) F Indium (In) F Tin (Sn) F Krypton (Kr) - Strontium (Sr) M Lanthanum ... Sb-132 M 8.1E-11 Forrest’s method Sb-132m M 1.2E-10 Forrest’s method Sb-133 M 8.4E-11 DCAL I-134m F 1.9E-11 DCAL Cs-139 F 7.4E-11 DCAL Ce-145 M 3.2E-11 DCAL Ce-146 M 1.6E-10 JAERI [25]...
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2016:12 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – engineered barriers, engineering geology and chemical inventory
(SKB 2010). The methodology involves ten steps (see Figure 2-4 of SKB 2014a, TR-14-01) including, (i) the handling of FEPs, (ii) description of the wastes, disposal facilities (existing and planned) and ... följd av frysning och tining av betong och bentonit vid förvaring av låg- och medelaktivt kärnavfall i SFR 1. SKB R-07-60, Svensk Kärnbränslehantering AB. (in Swedish). Gaucher, E.C. and Blanc, P., 2006...
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2005:15 Human Factors Engineering Plan for Reviewing Nuclear Plant Modernization Programs
HFE human factors engineering HRA human reliability analysis HSI human-system interface I&C instrumentation and control IAEA International Atomic Energy Agency IEC International Electrotechnical ... version of the review plan was then used to review of the major instrumentation 2 and control (I&C) system and control room modernization program at Unit 1 of the Oskarshamn Nuclear Power Station...
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97:26 3rd edition Reliability of Piping System Components
authors and do not necessarily coincide with those of the SKI. SKI Report 97:26 (3rd Edition) i Note to 3rd Edition This new edition includes an updated Appendix B. Since the publication of the ... projektarnbetet. Resultaten från arbetet utgörs av: (1) Händelsebaserad databas över intäffade skador i kärnkraftverk under perioden 1970-1997. Tyngdpunkten ligger på amerikanska ock nordiska drift- erfarenheter...
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2023:07 General data in accordance with the requirements in Article 37 of the Euratom Treaty
(Clab) on the Simpevarp Peninsula in Oskarshamn. The report follows the guideline set out in Annex I on the recommendation for applying Article 37 of the Euratom Treaty (2010/635/Euratom). The report ... would result in measurable dose levels in other Member States. According to the guideline in Annex I, no reporting of effective dose is required in other Member States provided that reporting is provided...
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2006:11 Engineered Barrier System Assessment of the Corrosion Properties of Copper Canisters
assumed: 2Cu + ½O2(g) o Cu2O A conservatively assumed consumption of all oxygen by oxidation to Cu(I) would correspond to about 2 mm of corrosion of the canister wall. This corrosion during the oxidizing ... bentonite buffer where the oxygen might enter. 5.2 Chloride Chloride forms strong complexes with Cu(I) and therefore facilitates mass-transfer limited corrosion near the canister-bentonite interface. Figure...
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98:29 Design Basis for the Copper/Steel Canister, Stage four, Final Report
understood that the finished casting was nominated I 6 and four further castings, I7 to I11have now been made in nodular iron. Two further inserts, I12 and I 13 are scheduled for production early in 1998. ... defect size versus depth in the specimen profile which detection equipment should be designed to meet. I did not ask for a copy of this since it was considered to be more appropriate that it should be supplied...
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2007:39 Influence of Crack Morphology on Leak Before Break Margins
162 kB ... morphology assumptions. 19 0 0.1 0.2 0.3 0.4 0.5 50 100 150 200 250 300 COD i with Resi COD o With Resi COD i No Resi COD o No Resi L (mm) Figure 5. COD for weld W2 in Surge line as function...
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2005:24 DECOVALEX III/BENCHPAR PROJECTS Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository
laboratory experiments. DECOVALEX II, started in 1996, built on the experience gained in DECOVALEX I by modeling larger tests conducted in the field. DECOVALEX III, started in 1999 following the completion ... obtained, as compared with the Task 2C results of DECOVAEX II. The measures taken for improvement were: i) Parameter changes (reduced rock mass permeability and rock mass thermal expansion by the SKI/KTH team...
Innehållstyp: Dokument