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Din avgränsning ger 42 träffar.

• 2007:07 DECOVALEX-THMC Project - Task A

  This report presents the definition of the first phase, Task A-1, of the Task A of the international DECOVALEX project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the...

  Innehållstyp: Publikationer

• 2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites

  An important part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be...

  Innehållstyp: Publikationer

• 2007:33 Analys av mänsklig tillförlitlighet HRA-begreppets tillämpbarhet vid revisionsavställning

  Analyser av mänsklig tillförlitlighet, Human Reliability Analysis (HRA) har använts under en längre tid i kärnkraftverkens probabilistiska säkerhetsanalyser. SKI har nyligen genomfört en utredning om befintliga metoder inom området HRA (litteraturstudie) och hur dessa metoder används av tillståndshavarna för de svenska kärnkraftverken...

  Innehållstyp: Publikationer

• 2007:31 Säkerhets- och strålskyddsläget vid de svenska kärnkraftverken 2006

  Säkerhetsproblemen i el-systemen vid reaktor Forsmark 1 var den dominerande händelsen i de svenska kärntekniska anläggningarna under 2006. Händelsen har fått stor betydelse för synen på tillförlitligheten när det gäller säkerhetssystems funktioner och har väckt stor internationell uppmärksamhet. I samband med SKI:s utredning...

  Innehållstyp: Publikationer

• 2007:26 Safety Culture Enhancement Project Final Report

  At the International Conference on Safety Culture in Nuclear Installations, organized by IAEA in 2002, one concluding remark was that the regulators should encourage a sincere interest in safety culture among licensees. In line with this SKI wanted to explore a proactive path to encourage the licensees in their safety culture work. SKI also had the ambition to gain more information on the MTO...

  Innehållstyp: Publikationer

• 2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister

  The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...

  Innehållstyp: Publikationer

• 2007:08 DECOVALEX-THMC - Task B

  This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...

  Innehållstyp: Publikationer

• 2007:11 Review of Quality Assurance in SKBs Repository Research Experiments

  SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...

  Innehållstyp: Publikationer

• 2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod

  The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...

  Innehållstyp: Publikationer

• 2007:04 Link Between RI-ISI and Inspection Qualification: Relationship between Defect Detection Rate and Margin of Detection

  A relationship has been established between defect detection ratio and margin of detection based on blind trails. The results are based on a rather small amount of data produced by personnel from one inspection laboratory but give us indications of how signal to noise ratio is possible to relate to the probability of detection (POD) used in RI-ISI models. The relationship need to be developed...

  Innehållstyp: Publikationer