Din avgränsning ger 110 träffar.
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2007:06 Probabilistic Safety Goals - Phase 1 -Status and Experiences in Sweden and Finland
257 kB...
Innehållstyp: Dokument -
2007:13 Elektrokemiska aspekter på korrosion i svenska reaktorinneslutningar
1246 kB...
Innehållstyp: Dokument -
2007:27 Kompetensöverföring på svenska kärnkraftverk i samband med pensionsavgångar
413 kB...
Innehållstyp: Dokument -
2007:39 Influence of Crack Morphology on Leak Before Break Margins
162 kB...
Innehållstyp: Dokument -
2007:37 Identification of Common Cause Initiating Events Using the NEA IRS Database
679 kB...
Innehållstyp: Dokument -
2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases
208 kB...
Innehållstyp: Dokument -
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