Visar 3291 sökträffar på ”WiFi-mätningar i skolmiljö”
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2015:38 Evaluation of fatigue in austenitic stainless steel pipe components
3424 kB ... fatigue limit in Langer equation C2 Secondary stress index defined in ASME [1] E Young’s modulus i Dummy index kM Slope of moment- nominal strain diagram K Fatigue reduction factor K2 Local stress ... 16 The equivalent measure for a load sequence consisting of m strain cycles with amplitude εa,i, is expressed in terms of the β-norm of the strain amplitudes. ԡ߳ԡఉ ൌ ൭ ͳ ݉߳ǡ ఉ ൱...
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2005:64 Investigating conceptual models for physical property couplings in solid solution models of cement
1626 kB ... Transition State Theory rate equation (e.g. Helgeson et al., 1984) of the form, ⎟⎟⎠ ⎞ ⎜⎜⎝ ⎛ −= 1 i i ii i K QAk dt dC . Here ik (mol m -2 y-1) is the rate of the reaction per surface area of end member ... occupied by the minerals is therefore ∑ iiMvNθ m3, where Mvi denotes the molar volume of mineral i (m3/mol). Thus 1MvN ii =+ ∑θθ , and so † Taken...
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2021:14 Reliability, Feasibility and Significance of Measurements of Conductivity and Transmissivity of the Rock Mass for the Understanding of the Evolution of a Repository of Radioactive Waste
Backers T.2), Eberhardt E.3), Fisher B.3), Geier J.4), Kwon S.5), Min K-B.5), Blaheta R.6), Hančilová I.6), Hasal M.6), Říha J.6) & Lanaro, F.7) 1)geomecon GmbH, Germany 2)Ruhr-Universität Bochum, Germany ... 2), Eberhardt E. 3), Fisher B. 3), Geier J. 4), Kwon S. 5), Min K-B. 5), Blaheta R. 6), Hančilová I. 6), Hasal M. 6), Říha J. 6) & Lanaro, F. 7) 1) geomecon GmbH, Germany 2) Ruhr-Universität Bochum...
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00:56 The Application of State-Level Integration of Safeguards in Sweden. Final Report
.......................................5 1.3.6 Nuclear related production (INFCIRC/540 2a iv Annex I) .......................................5 1.3.7 Nuclear related research and development .......... ... short distance by the Ringhals plant. 1.3.6 Nuclear related production (INFCIRC/540 2a iv Annex I) Sweden has facilities for the production of control rods, zirconium fuel channels and zirconium tubes...
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2004:09 Low Temperature (320°C and 340°C) Creep Crack Growth in Low Alloy Reactor Pressure Vessel Steel
ways to produce the coarse grained HAZ; by welding and by simulating. Advantages of simulating are to i) give distinguished welding parameter, ii) reduce scatter in testing results caused by inhomogeneities ... in the coarse grained HAZ of ASTM A508 low alloy reactor pressure vessel steel, this project aims at i) studying creep and CCG behaviour at 320°C and 340°C, ii) investigating creep damage, and iii) performing...
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2013:10 Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing
work was nished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was re- garded to be of more general interest it was published again as a research ... 1.2 References [1.1] Krosness A., Spång K. ”Miljökvalificering av komponenter i kärnkraftverk. Del I: Komponenter i reaktorinneslutningen”, IFM Akustikbyrån TR 5.082.01, 2:nd edition, september 1980...
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Design premises KBS-3V repository report.pdf
och anläggningens drift Kapitel 5 Anläggnings- och funktionsbeskrivning Kapitel 6 Radioaktiva ämnen i anläggningen Kapitel 7 Strålskydd och strålskärmning Kapitel 8 Säkerhetsanalys Repository production ... miljökonsekvens- bedömning Vattenverksamhet Laxemar-Simpevarp Vattenverksamhet i Forsmark I Bortledande av grundvatten Vattenverksamhet i Forsmark II Verksamheter ovan mark Avstämning mot miljömål Comparative...
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2005:34 An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago (pdf 2,24MB)
and Dismantling Implementation................................................... 3-1 3.2.1 Phase I - Map Tube Facility Characterization............................................. 3-1 3.2.2 Phase II ... characterization was conducted. For Area 317, the characterization process was reported in, “ANL Area 317 Phase I & II Characterization Report” (ANL-TR-0001). The process of evaluating SWMUs within the 317/319/ENE...
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99:08 Human Factors Aspects of Non-Destructive Testing in the Nuclear Power Context
kontrollera material t.ex., komponenter i ett kärnkraftverk. För att säkerställa kärnkraftverkens integritet utförs återkommande provning av komponenter medan de är i drift. För att säkerställa dessa provningars ... vilken utrustning som skall användas och hur den skall användas. Dessutom hjälper proceduren provaren i bedömningen av indikationer. Det finns flera faktorer som kan påverka kvaliteten hos en provning (t...
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97:26 1st edition Reliability of Piping System Components
Influence Matrix - An Example ………………………………… 52 4-6 Overall Range of Effect of Influence on Reliability (i)………… 53 4-7 Overall Range of Effect of Influence on Reliability (ii)………… 53 4-8 Evaluation of Plant-Specific ... 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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