Din avgränsning ger 2180 träffar.
-
2005:21 DECOVALEX III PROJECT Thermal-Hydrological Modeling of the Yucca Mountain Project Drift Scale Test
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 ... the DST experiment at Yucca Mountain. The double structure approach is 16 D E C O V A L E X I I I- P r o je c t : ta s k 2 B T e m p e ra tu re e v o lu t io n (b o r e h o le 1 5 8 ) 2 0...
Innehållstyp: Dokument -
00:33 Evaluation of Colloid Transport Issues and Recommendations for SKI Performance Assessment
.................... Date ................... Sign .................… Date .................…. i Contents Summary ................................................................................. ... effects of colloid transport through the geosphere to be potentially significant (NAGRA’s Kristallin-I, Japan’s H-12, HMIP’s Sellafield Assessment, Nirex’s Nirex 97, and the US DOE’s TSPA-VA for Yucca Mountain)...
Innehållstyp: Dokument -
2008:10 International Expert Review of SR-Can: Engineered Barrier Issues
SR-Can. SKB planerar att lämna in en ansökan om uppförande av ett slutförvar för använt kärnbränsle i Sverige under 2010. Som underlag till ansökan kommer SKB presentera en säkerhetsrapport, SR-Site, som ... konsekvenser. Som en förberedelse inför SR-Site publicerade SKB den preliminära säkerhetsanalysen SR-Can i november 2006. Syftena med SR-Can är bl.a. att redovisa en första bedömning av den långsiktiga säkerheten...
Innehållstyp: Dokument -
2007:22 Safety Management An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts
and/or improving safety management in the nuclear power industry and its regulators. Sammanfattning I denna rapport introduceras först ett systemperspektiv på säkerhetshantering (safety management) följt ... studien ett vägtunnelsystem. Riskerna för en bilolycka i det första fallet är uppenbara. Den stora exponeringen genererar många incidenter och olyckor. I den andra studien skapar den relativt låga trafikintensiteten...
Innehållstyp: Dokument -
2012:07 Implementation of the Master Curve method in ProSACC
902 kB ... (5) , 20 )20( 41 1 4 (i) 0 N i Jc N K K where N denotes the number of valid tests (six minimum). Note ... opened to fill the input data in evaluation of the Master Curve toughness, as shown in Fig. 3.2: i) There is a valid T0 value from fracture toughness testing on the actual material. ii) There is valid...
Innehållstyp: Dokument -
99:55 Risk Based Test Interval and Maintenance Optimisation Application and Uses
Sammanfattning I denna rapport redovisas det arbete som har genomförts inom projektet “Risk Based Test Interval and Maintenance Optimisation – Application and Uses”. Projektet är en del i ett samordningsprojekt ... undersökning gjorts av de osäkerheter som finns i resultaten med avseende på detaljeringsgrad, val av metod osv. Fyra olika testintervall har undersökts i analysen. Förutom en ursprunglig optimering har...
Innehållstyp: Dokument -
2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
combined in pairs and allow the com- parison for full fatigue cycles each transient is input in pairs, i. e. in full tem- perature cycles. This means that the temperature change displayed in Figure A2 is ... The default SSM 2011:30 21 values correspond to the most conservative settings possible, i. e. those that give a high Fen as possible. For the temperature, DST recommends using the average...
Innehållstyp: Dokument -
02_1585177_Corrected_waste_volumes.pdf
367 kB ... Stockholm. Blekholmstorget 30, Telefon: 08-459 84 00. Fax: 08-579 386 10 skb.se Org.nr: 556175-2014. Säte i Stockholm. skb.se 1 Background The radionuclide transport models used in the calculations...
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 -
2010:01 Licensing of safety critical softwarefor nuclear reactors
2090 ... ...............................................................................................7 I INTRODUCTION ...................................................................................... ... software based systems; – as guidance for system design specifications by manufacturers and major I&C suppliers on the international market. SSM 2010:01 Document Structure From the outset,...
Innehållstyp: Dokument